ML18151A292
| ML18151A292 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1991 |
| From: | Erickson D, Noce C, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 92-270, NUDOCS 9205040236 | |
| Download: ML18151A292 (117) | |
Text
{{#Wiki_filter:. ~ ........ VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 29, 1992 United States Nuclear Regulatory Commission Serial No. 92-270 Attention: Document Control Desk NURBP Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Attached is the 1991 Radiological Environmental Monitoring Program Report for Surry Power Station which fulfills the requirement for the Annual Radiological Environmental Operating Report per Technical Specification 6.6.b.2. Very truly yours, WttiJ\ W. L. s<ewart Senior Vice President - Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
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- .. Surry Power Station Radio"/ogical Environmental Monitoring Program For1991
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Annual, Radiological Environmental operating Report Surry Power Stanon January 1, 1991 to December 31, 1991 Prepared by: Engineering Reviewed by: Peter F. Blount Supervisor Radiological Analysis Reviewed by: Barry A. Garber Supervisor Technical Services, Health Physics Approved by: Dean L. Erickson Superintendent Radiological Protection 2
Table Of Contents e Section Title Page* Forward ................................................................................................ 7 Executive Summary ................................................................................... 8 I. Introduction ..................................................................................... 11 II. Nuclear Power And The Environment: In Perspective ................... 13 III. Sampling And Analysis Program ..... ,............................................. ;. 26 N. Program Exceptions ........................................................................ 37 V. Summary And Discussion Of 1991 Analytical Results ...................... 39 A. Airborne Exposure Pathway ....................................................... 40
- 1. Air Iodine/Particulates ........................................................... 40 B. Waterborne Exposure Pathway ................................................. .42
- 1. River Water ............................................................................ 42
- 2. Well Water ............................................................................ 43 C. Aquatic Exposure Pathway ................................................... ;..... 44
- 1. Silt ......................................................................................... 44
- 2. Shoreline Sediment. ............................................................... 47 D. Ingestion Exposure Pathway ...................................................... 47
- 1. Milk .......................................................................................47
- 2. Fish ........................................................................................ 50
- 3. Food Products ....................................................................... 52 E. Direct Radiation Exposure Pathway ........................................... 51
- 1. TI.D Dosimeters ..................................................................... 51 VI. Conclusion ...................................................................... :............... 53 3
Table of Contents (Continued) Section Title Page VII. References ....................................................................................... 56 VIII. Appendices ...................................................................................... 57 Appendix A - Radiological Environmental Monitoring Program Annual Summaiy Tables - 1991 ................ 57 Appendix B - Data Tables ............................................................... 60 Appendix C - Land Use Census - 1991 ............................................ 78 Appendix D - Synopsis of Analytical Procedures ............................ 79 Appendix - EPA Interlaboratory Comparison Program .................... 90 Ust of Trending Graphs
- 1. Gross Beta in Air Particulates ......................................................... .41
- 2. Tritium in River Water ..................................................................... 43
- 3. Tritium in Well Water ...................................................................... 44
- 4. Cobalt-58 in Silt ............................................................................... 45
- 5. Cobalt-60 in Silt ............................................................................... 45
- 6. Cesium-134 in Silt ............................................................................ 46
- 7. Cesium-137 in Silt ............................................................................ 46
- 8. Cobalt-58 in Clams .......................................................................... 49
- 9. Cobalt-60 in Clams .......................................................................... 49
- 10. Cesium-137 in Clams ....................................................................... 50
- 11. Direct Radiation Measurements-TIO Results ................................... 52 4
Table of Contents (C<mtinued) list Of Figures Figure Title Page
- 1. Atomic Structure .............................................................................. 13
- 2. Alpha Particle .................................................................................. 15
- 3. Beta Particle ............................... ;..................................................... 15
- 4. Gamma Ray ..................................................................................... 15
- 5. The Penetrating Ability of Various Types of Radiation .................... 16
- 6. Unit Comparison ............................................................................. 16
- 7. The Curie, a Measurement of Activity ............................................. 17
- 8. Average Annual Dose Equivalent to Persons in the U.S.
from Various Radiation Sources ....................................................... 18
- 9. Estimated Average Days of Life Expectancy Lost Due to Various Health Risks ........................................................................ 20
- 10. Reactor Vessel with Fuel Assemblies, Rods, and Fuel Pellets .......... 21
- 11. Fission: a Chain Reaction ................................................................. 22
- 12. PWR System Diagram ...................................................................... 23
- 13. Containment Schematic ................................................................... 24
- 14. Surry Radiological Monitoring Locations ......................................... 29 5
List Of Tables Table Page 1 Uranium Isotopes ............................................................................ 14 2 Radiological Sampling Station Distance and Direction from Unit 1 ..................................................................... :................ 27 3 Surry Power Station Sample Analysis Program ................................ 34 4 REMP Exceptions For Scheduled Sampling and Analysis During 1991 ....................................................................... 38 5 Gross Beta Analysis Summary ........................................................ .40 Appendix B Tables B-1 Iodine-131 Concentration in Filtered Air ......................................... 60 B-2 Gross Beta Concentration in Air Particulates ................................... 62 B-3 Gamma Emitters Concentration in Quarterly Air Particulates ................................................................................. 64 B-4 Gamma Emitter and Tritium Concentrations in River Water ............ 66 B-5 Gamma Emitter and Tritium Concentrations in River Water - State Split Samples ..................................................... 68 B-6 Gamma Emitter and Tritium Concentrations in Well Water ................................................................. :..................... 69 B-7 Gamma Emitter Concentrations in Silt ............................................. 70 B-8 Gammma Emitter Concentrations in Shoreline Sediment .......................................................................... 70 B-9 Gamma Emitter, Strontium-89, and Strontium-90 Concentration in Milk ...................................................................... 71 B-10 Gamma Emitter Concentration in Clams ......................................... 73 B-11 Gamma Emitter Concentration in Oysters ....................................... 74 B-12 Gamma Emitter Concentration in Crabs .......................................... 75 B-13 Gamma Emitter Concentration in Fish ............................................ 75 B-14 Gamma Emitter Concentration in Vegetation .................................. 75 B-15 Direct Radiation Measurements - Quarterly TID Results Set 1 ........ 76 B-16
- Direct Radiation Measurements - Quarterly TID Results Set 2 ........ 77 6
Forward e This report is submitted as required by Technical Specification 6.6.B.2, Annu~ Radiological Environmental Operating Report for Suny, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281. 7
Executive Summary This document is a detailed report of the 1991 Surry Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 1991 in air, water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated, and summarized. The REMP is designed to ensure that radiological effluent releases are As Low As is Reasonably Achievable (AI.ARA), no undue environmental effects occur, and the health and safety of the public is protected. The program also detects any unexpected environmental processes which could allow radioactive accumulations in the environment or food pathway chains. Radiation and radioactivity in the environment is con-stantly monitored within a 25 mile radius of the station. Virginia Power also collects samples within this area. A number of sampling locations for each medium were selected using available meteorological, land use, and water use data. Two types of samples are taken. The first type, control samples, are collected from areas that are beyond measurable influence of Surry Nuclear Power Station or any other nuclear facility. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than Surry Power Station, can thus be compared to the environment surrounding the nuclear power station. Indicator samples are the second sample type obtained. These samples show how how much radiation is contributed to the environ-ment by the plant. Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration. Prior to station operation, samples were collected and analysed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline." Analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations, other causes such as the Chernobyl accident, or natural variation. Teledyne Isotopes provides sample analyses for various radioisotopes as appropriate for each sample media. *Participation in the Environmental Protection Agency's (EPA) Interlaboratory Comparison Program provides an independent check of sample measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis values frequently fall below the minimum detection limits of state-of-the-art measurement methods. Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for radiological environmental monitoring must be able to detect specified minimum Lower Limits of Detection (LLD). This ensures that analyses are as accurate as possible. Samples with extremely low levels of radiation which cannot be detected are therefore reported as being below the LLD. The NRC also mandates a "reporting level." Licensed nuclear facilities must report any releases 8
0 equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level. Analytical results are divided into five categories based on exposure pathways: Airborne, waterborne, aquatic, ingestion, and direct radiation. Each of these pathways is describe below:
- The airborne exposure pathway includes airborne iodine and airborne particulates. The 1991 airborne results were very similar to previous years and to preoperational levels. No increase was noted and there were no detections of fission products or other man-made isotopes in the airborne particulate media during 1991.
- The waterborne exposure pathway includes well water and river water. Two river water samples from the Surry Discharge Canal indicated cesium-137 at levels slightly above the required LLD. No other river water samples indicated the presence radioisotopes except tritium and naturally occurring potassium The average tritium activity in 1991 was less than 2.0% of the NRC reporting level. No man-made or naturally occurring isotopes were detected in well water. This trend is consistent throughout the operational monitoring program
- The aquatic exposure pathway includes silt and shoreline sediment samples. Silt contained some cesium-137, cesium-134, cobalt-58, and cobalt-60. During the preoperational period, there were no man-made isotopes detected for this pathway. Man-made isotopes have accumulated. Gamma-emitting isotope concentrations in 1991, however, indicate a decreasing trend compared to the previous five year period. Shoreline sediment, which may provide a direct exposure pathway, contained no man-made isotopes. Naturally occurring isotopes detected in 1991 sediment samples revealed a steady trend over the recent past.
- The ingestion exposure pathway includes milk, aquatic biota, and food product samples.
Iodine-131 was not detected in any 1991 milk samples and has not been detected in milk prior to or since the 1986 Chernobyl accident. Strontium-90, attributable to past atmospheric nuclear weapons testing, was detected at levels less than the previous years and lower than preoperational years. Naturally occurring potassium-40 was detected at average environmental levels. The aquatic biota exposure pathway includes samples taken from localized populations of crabs, fish, clams, and oysters. One clam sample had a cesium-137 concentration equivalent to 1.2% of the NRC reporting level. Naturally occurring potassium-40 was detected in each of the aquatic biota samples at average environmental levels. Vegetation samples revealed naturally occurring potassium-40 and beryllium-7 at levels which are lower than the previous years samples. Cesium-137 was detected in one sample at concentrations less than the average for the previous five years.
- The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (1LDs). 1LD results have indicated a continual decrease over the past six years.
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During 1991, as in previous years, operation of the Suny Nuclear Power Station created no adverse environmental affects or health hazards. The maximum dose calculated for the hypothetical individual at the Suny Power Station site boundary due to liquid and gaseous effluents released from the site during 1991 was 0.233 millirem For reference this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1 %. These results demonstrate not only compliance with federal and state regulations, but also demonstrate the adequacy of radioactive effluent control at the Surry Nuclear Power Station. 10
L Introduction The operational Radiological Environmental Monitoring Program (REMP) conducted for the year 1991 for Surry Power Station is provided in this report. The results of measurements and analyses of data obtained from samples collected from January _1, 1991 through December 31, 1991 are summarized. A. The Surry Power Station of Virginia Electric and Power Company is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 822.6 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May 1, 1973. ., . B. The United States Nuclear Regulatory Commission (USNRC) regulations (10 CFR 50.34a) require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas As Low As is Reasonably Achievable (AI.ARA). To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications which address the release of radioactive effluents. Inplant monitoring is used to ensure that these release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in Virginia Power's Station Administrative Procedure VPAP-2103, Offsite Dose Calculation Manual (ODCM).
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C. Virginia Electric and Power Company is responsible for collecting the various indicator and control environmental samples. Teledyne Isotopes is responsible for sample analysis and e submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared to control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This pre-operational data is compared to data collected during the operational phase to assist in evaluating any radiological impact of plant operations. D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatoiy Guide 4.8 and Suriy Power Station's ODCM. These concentrations are based upon the annual dose commitment recommended by 10 CFR 50, Appendix I, to meet the criterion of "As I.ow As Is Reasonably Achievable." E. This report documents the results of the Radiological Environmental Monitoring Program for 1991 and satisfies the following objectives of the program:
- 1. Provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.
- 2. To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.
- 3. To identify changes of radioactivity in the environment.
- 4.
- To verify that the plant operations have no detrimental effect on the health and safety of the public..
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IL Nuclear Power And The Environment: In Perspective Coal, oil, natural gas, nuclear power, and hydropower have all been used to run the nation's electric generating stations. Each method, however, has its drawbacks. Coal-fired power can damage the environment during the mining process, or by airborne discharges such as fly-ashand chemicals which contribute to acid rain.. Oil and natural gas are costly because of their limited supply. Few suitable sites for hydropower exist, and building the large dams necessary to produce Hydropower has a significant impact on the environment. Nuclear energy provides an alternate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, hundreds of acres adjoining Surry Power Station are a state waterfowl refuge, and Lake Anna, next to North Anna Power Station, is a well-known fishing site with a state park on its shore. In order to more fully understand this unique energy source, background information about basic radiation characteristics, risk assessment, reactor operation, effluent control, environmental monitoring, and radioactive waste is provided in this section. Fundamentals TbeAtom Everything we encounter is made of atoms. Atoms are the smallest parts of an element that still have all the chemical properties of that element. At the center of an atom is a nucleus. The nucleus consists of neutrons and protons. Electrons move in an orbit around the nucleus and are negatively charged. Protons and neutrons are nearly identical in size and weight, and each is about 2000 times heavier than an electron. The proton, however, has a positive charge, while the neutron has no charge, it is electrically neutral. Figure 1 presents a simple diagram of an atom.
.......-.-*~* Protons *
.-*-* Positive Charge *
- Nucleus 0 Neutrons Neutral Charge
- KC565 Figure 1. Atomic Structure 13
Isotopes The number of protons in the atom of any specific element is always the same. For example, all hydrogen atoms have one proton whereas all oxygen atoms have eight protons. Unlike protons, the number of neutrons in the nucleus of an element may vary. Atoms with the same number of protons, but a different number of neutrons, are called isotopes. Table 1 lists the isotopes of uranium. Isotopes Sy Number Number of Protons of Neutrons Uranium-235 23su 92 143 Uranium-236 236u 92 144 Uranium-237 237U 92 145 Uranium-238 235u 92 146 Uranium-239 239lJ 92 147 Uranium-240 240 148 0 92 Table 1. Uranium Isotopes Radianon and Radioacnvity
- Radionuclides Normally, the parts of an atom are in a balanced or stable state. A small percentage of atoms naturally contain excess energy and therefore are not stable atoms. If the nucleus of an atom contains excess energy, it may be called a radioactive atom, a radioisotope, or radionuclide. The excess energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom Radionuclides can be naturally occurring, such as uranium-238, thorium-232 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt-60.
Radioactive Decay Radioactive atoms attempt to reach a stable (non-radioactive) state through a process known as radioactive decay. Radioactive decay is the release of energy from the atom through the emission of particulate and/or electromagnetic radiation. Particulate radiation may be in the form of electrically charged particles such as alpha (2 protons plus 2 neutrons) or beta particles (1 electron), or may be electrically neutral, such as neutrons. Part of the electromagnetic spectrum consists of gamma rays and X-rays which are similar to light and microwaves, but have a much higher energy. Haff-Life
- A radioactive half-life is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Cobalt-60 has a half-life of about 5 years.
14
I - -- - - - - - - - After 5 years, 50% of its radioactivity is gone, and after 10 years, 75% has decayed away. Radioactive half-lives vary from millionths of a second to millions of years. Radioactive atoms may decay directly to a stable state or may.undergo a series of decay stages. During the decay process, several daughter products may be formed which eventually transform into stable atoms. Naturally occurring radium-226, for example, has 10 successive daughter products (including radon) resulting finally with lead-206 as a stable form. Types OfRadiation Two types of radiation are considered in the nuclear industry, particulate--and electromagnetic. Particulate radiation may come from the nucleus of an atom in the form of an ejected alpha particle. Alpha particles consists of two pro-tons together with two neutrons. Alpha particles have a very limited ability to penetrate matter. A piece of paper will stop all alpha radiation. For this reason, alpha radiation from sources outside the body are not considered to be a radiation hazard. KC566 Figure 2. Alpha Particle A beta particle is like an electron that has been ejected from the nucleus of an atom. The outer layers of skin or a thin piece of plastic will stop beta radiation. Exposure to beta radiation can be a hazard to the skin or lens of the eye. Because of their limited ability to penetrate the body, beta and alpha radiation are a health concern primarily if swallowed or in-haled where they might cause internal KC567 radiation exposure.
. Figure 3. Beta Particle Gamma rays are like X-rays, except that they come from the nucleus of an atom while X-rays come from the electron rings. Gamma rays can penetrate deep into the body and thus give a "whole-body radiation dose. Several inches of concrete or lead will stop both gamma and X-rays. Figure 5 shows the approximate penetrating ability of various types of radiation. KCS68 Figure 4. Gamma Ray 15
- a.=Alpha 13 = Beta r= Gamma Radioactive Material Paper Aluminum Concrete As radiation travels, it collides with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper, beta particles by a thin sheet of aluminum, and gamma radiation by several inches of concrete or lead.
KC564 Quantities And Units OfRadioactive Measurement Several quantities and units are used to describe radioactivity and its effects. In the following sections two terms, rem and activity, will be used to describe amounts of radiation. Rem measures the potential effect of radiation exposure on human cells. Small doses are counted in millirem. Each millirem is equal to one thousandth of a rem. Federal standards limit exposure for an individual member of the public to 500 millirem annually. This annual limit does not include the average 300 millirem received from natural sources and approximately 60 millirem from medical applications. n 1 inch 1 millirem Just as Twelve inches equals one foot 1000 millirem equals 1 rem KC561 Figure 6. Unit Comparison * ; 16
Activity is the number of nuclei in a sample that disintegrate (decay) ev-ery second. Each time a nucleus disin-tegrates, radiation is emitted. The unit of activity is the Curie. A Curie (Ci) is the amount of radioactive material which decays at a rate of 37 billion atoms per second. Smaller units of the Curie are often used. Two common
~1Cun8 ,
units are the microCurie (uCi), one millionth of a Curie, and the picoCurie (pCi), one trillionth of a Curie. A Curie Lil 10 Tons of Thorium-232 1 Gram of Radium-226 is a measurement of radioactivity, not (radiation source) (radiation source) a quantity of material. The amount of One gram of radium-226 and.10 tons of thorium-232 material necessary to make one Curie are both approximately 1 Curie. KC569 J
- ,.. ~ - ~ < j varies. For example,* one gram of Figure 7. The Curie, a Measurement radium-226 is one Curie of radioactiv- of Activity
- ity, but it would take 9,170,000 grams - ... _.... -* ~ ~ ~ ~-"*'* --- ... ""-*~~"" --~~- - --
(about 10 tons) of thorium-232 to obtain one Curie. Sources OfRadiation Background Radiation Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. Mankind has always lived with radiation and always will. Every second of our lives, over 7,000 atoms undergo radioactive decay in the body of the average adult. Radioactivity exists naturally in the soil, water, air and space. All of these common sources of radiation contribute to the natural background radiation that we are exposed to each day. The earth is constantly showered by a steady stream of high energy gamma rays. These rays come from space and are known as cosmic radiation. Our atmosphere shields out most of this radiation, but everyone still receives about 20 to 50 millirem each year from this source. At high altitudes, the air is thinner and provides less protection from cosmic radiation. Because of this, people living at higher altitude~ or even flying in an airplane are exposed to more radiation. Radioactive atoms commonly found in the atmosphere as a result of cosmic ray interactions include beryllium-7, carbon-14, tritium, and sodium-22. Other natural sources of radiation include radionuclides naturally found in soil, water, food, building materials and even people. People have always been radioactive, in part because the carbon found in our bodies is a mixture of all carbon isotopes, both non-radioactive and radioactive. Approximately two-thirds of the whole body dose from natural sources is contributed by radon gas. About one-third of the naturally occuring external terrestrial and internal whole body radiation dose is attributable to a naturally radioactive isotope of potassium, potassium-40. 17
Man-Made In addition to naturally occurring radiation, people are also exposed to man-made radiation. The largest sources of these exposures are from medical X-rays, fluoroscopic examinations, radioactive drugs, and tobacco. Small doses are received from consumer products such as television, smoke al~, and fertilizers. Very small doses result from the production of nuclear power. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, carbon-14, and tritium. Man-Made Sources Nuclear Power (0.1 %) Miscellaneous (0.1 %)
~ - - Occupational (1.4%)
ManaMade Medical Natural And. ManmMade Sources Diagnostic X-Rays 39.00 Other Medical 14.00 Consumer Products 5.00 to 13.00 Occupational 0.90 Miscellaneous Environmental 0.06 Nuclear Power 0.05 Natural Background Radon and Radon Daughters 200.00 Cosmic Rays 27.00 Cosmogenic Radiation 1.00 Terrestrial Radiation 28.00 Internal Radiation 40.00 Total 360.00 MREM Per Year NCRP Report No. 93, "Ionizing Radiation Exposure of the Population of the United States,* 30 Dec 1987, Bethesda, MD 20814 KC563
. Figure 8. Average Annual Dose Equivalent To Persons In The ,
U.S. From Various Radiation Sources 18
Effects OfRadiation 1 9 Studies The effects of ionizing radiation on human health have been under study for more than eighty
. years. Scientists have obtained valuable knowledge through the study of laboratory animals that were exposed to radiation under controlled conditions. It has proven difficult, however, to relate the biological effects of irradiated laboratory animals to the potential health effects on humans.
Because of this, human populations irradiated under various circumstances have been studied in great depth. These groups include:
- Survivors of the atomic bomb.
- Persons undergoing medical radiation treatment.
- Radium dial painters during World War I who ingested large amounts of radioactivity by "tipping" the paint brushes with their lips.
- Uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore).
- Early radiologists, who accumulated large doses of radiation from early X-ray equipment while being unaware of the potential hazards.
Analysis of these groups has increased our knowledge of health effects resulting from large radiation doses. Less is known about the effects oflow doses ofradiation. To be on the conservative side, we assume that health effects occur proportionally to those observed following a large dose of radiation. That is, if one dose of radiation causes an effect, then half the dose will cause half the effect Radiation scientists agree that this assumption overestimates the risks associated with low level radiation exposure. The effects predicted in this manner have not been actually observed in individuals exposed to low level radiation. Health Risks Since the actual effects of exposure to low level radiation are difficult to measure, scientists often refer to the possible risk involved. The problem is one of evaluating alternatives, of comparing risks and weighing them against benefits. People make decisions involving risks every day, such as deciding whether to wear seat belts or smoke cigarettes. Risks are a part of everyday life. The question is to determine how great the risks are. We accept the inevitability of automobile accidents. Building safer cars or wearing seat belts will reduce the risk of injury. You could choose to not drive to be even safer, but pedestrians and bicyclists are also injured by cars. Reducing the risk of injury from automobiles to zero requires moving to a place where there are no automobiles. 19
While accepting the many daily risks of living, some people feel that their demands for energy should be met on an essentially risk-free basis. Attention is focused on safeguarding the public, developing a realistic assessment of the risks, and placing them in perspective. Because you cannot see, feel, taste, hear, or smell radiation, it is often a source of concern. We have the same lack of sensory perception for things such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. Although these risks are just as real as the risks associated with radiation, they have not generated the same degree of concern as radiation. Most risks are with us throughout our lives, and their effects can be added up over a lifetime to obtain a total effect on our life span. The typical life span for an American woman is now 76 years, whereas men average 71 years of age. Figure 9 shows a number of different factors that decreased our average life expectancy. Days Activity 2500
- 1. Smoking 1 Pack of Cigarettes a Day
- 2. Being 20% Overweight 2000 3. Construction
- 4. Agriculture 1500 5. Auto Accidents
- 6. Avg Alcohol Consumption per Person
- 7. Home Accidents 1000
- 8. All Industry Hazards
- 9. Radiation Dose of 6.5 Millirem per 500 Year for 30 Years NCRP Report No. 95, "Radiation Exposure of the U.S.
Population from Consumer Products and Miscellaneous 0 Sources," National Council on Radiation Protection and Measurements, 30 Dec 1987, Bethesda, MD 20814 1 2 3 4 5 6 7 8 9 KC562 Figure 9. Estimated Average Days Of Life Expectancy Lost
- Due To Various Health Risks -
'.t.
The American Cancer Society estimates that about 30 percent of all Americans will develop cancer at some time in their lives from all possible causes. So, in a group of 10,000 people it is expected that 3,000 of them will develop cancer. If each person were to receive a radiation exposure of one rem in addition to natural background radiation, then it is expected that three more may develop cancer during their lifetime. This increases the risk from 30 percent to 30.03 percent. Hence, the risks of radiation exposure are small when compared to the risks of everyday life. These comparisons should give you some idea of the risk involved in activities that you are familiar with. They give a basis for judging what smoking, eating, or driving a car could mean to your health and safety. Everyone knows that life is full of risks. If you have the basis for judgment, you can decide what to do or what not to do. 20
Nuclear Reactor operation
- Electricity in the United States is being produced using fossil fuel, uranium, or falling water.
A fossil-fueled power station burns coal, oil or natural gas in a boiler to produce energy. Nuclear power stations use uranium fuel and the heat produced from the fission process to make energy. In both cases, they heat and boil water to produce steam. The steam is used to drive a turbine which turns a generator and produces electricity. Nuclear Fuel Uranium (U) is the basic ingredient in nuclear fuel, consisting of U-235 and U-238 atoms. Natural uranium contains less than one percent U-235 when it is mined. Commercial nuclear power plants use fuel with a U-235 content_of approximately three percent. The process used to increase the U-235 concentration is known as enrichment. Reactor operation After enrichment, the uranium fuel is chemically changed to uranium dioxide, a dry black powder. This powder is compressed into small ceramic pellets. Each fuel pellet is about 3/4 inches long and 3/8 inches in diameter. The pellets are placed into 12 foot long metal tubes made of zirconium alloy to make a fuel rod. About five pounds of pellets are used to fill each rod. A total of 204 fuel rods make a single fuel assembly. Virginia Power nuclear reactors contains 157 fuel assemblies (Figure 10). Reactor Vessel Fuel Rod Control Rods Coolant Outlet Nozzle Coolant Inlet Nozzle Fuel Rod Assembly Fuel Pellet Fuel Rod Assemblies Thermal Shield Core Support MT424 Figure 10. Reactor Vessel With Fuel Assemblies, Rods, and Fuel Pellets : 21
Fission Nuclear energy is produced by a process called fission. Fission occurs in a reactor when uranium is split into fragments producing heat and releas-ing neutrons. These neutrons strike other uranium atoms, causing them to split (fission) and release more heat and neutrons. This is called a chain reaction (Figure 11) and is controlled by the use of reactor control rods. e HeavyAtom o Free Neutron Q Fission Fragment 'VW> Heat Control rods are an essential part of the nuclear reactor. Control rods contain cadmium, indium, and silver metals which absorb and control the amount of neutrons produced in the reactor. The control rods act to slow down or stop the chain reaction. A chain reaction cannot occur when the control rods are inserted completely into the core. When the control rods are withdrawn, the chain reaction begins and heat is generated. Design & operation Surry Power Station and North Anna Power Station use a Pressurized Water Reactor (PWR) system to generate electricity. There are two complete and independent PWR systems on-site at both Surry and North Anna Power Stations. These are referred to as Unit-1 and Unit-2. The reactor core is inside a large steel container called the Reactor Pressure Vessel. The reactor core is always surrounded by water. The fissioning of the uranium fuel makes the fuel rods get hot. The hot fuel rods heat the water, which serves as a coolant that carries away heat. In a pressurized water reactor, heat is moved from place to place by moving water, the reactor's coolant. The water flows in closed loops. As (primacy) water moves through the core it gets very hot (605°F), but because it is under such high pressure, 2235 pounds per square inch (psi), it doesn't boil. The hot water then flows to the steam generator. The steam generator is a heat exchanger. Reactor coolant passes through it but doesn't mix with the steam generator (secondary) water. Instead, heat from the primary water is transferred through thousands of tubes to the cooler secondary water. The water in the steam generator is under much less pressure, and the heat boils the secondary water to steam. At Virginia Electric and Power stations, each unit has 3 steam generators. The steam is piped to a steam turbine that turns an electric generator. The exhausted steam from the turbine is cooled and converted back to water in a condenser. The condenser is also a heat exchanger; in it heat passes from the steam to a third loop of water. In Surry's case the James River provides the third loop water. At North Anna Power Station third loop water is from Lake Anna. The steam turns back to liquid and is pumped back to the steam generator. Figure 12 is a diagram of typical nuclear reactor systems. 22
- High Pressure Safety Injection System (Emergency Core Cooling)
- Low Pressure Safety Injection System (Emergency Cora Cooling)
- Containment Spray System
~ Main Steam System
- Reactor Cooling System (Primary Cooling System)
~ Condenser Cooling System
- Main Feedwater System
= Auxiliary Feed Water System Venfilation Turbine Building Release Stack
¥ Radiation Monitor Main Electrical Pressuriz Gene ator Electrical Power Auxiliary Building Relief Tan To Transmission System Charcoal Filter Containment Spray Pump e Or River Containment Sump KC560 Containment Nuclear power plants are designed to prevent the escape of large quantities of radiation and radioactive substances. Two principles are used. First, thick, heavy walls are used as shielding to absorb radiation and prevent its escape. Second, strong, airtight walls called containment, are used to prevent the escape of radioactive materials.
The reactor pressure vessel and the containment building thathouses it are enormously strong (Figure 13). Strong enough, in fact, to withstand a direct hit from a 707 jetliner. The reactor core lies within a sealed pressure vessel. Like all boilers its walls must be very strong because the water inside must be kept under high pressure. The reactor pressure vessel in a nuclear power plant is even heavier than an ordinary steam boiler because of the need to minimize the chance of rupture and release of any radioactive materials. The reactor pressure vessel is made from a stainless steel alloy 6 to 8 inches thick. Around the reactor pressure vessel is a thick concrete wall. This wall acts as shielding, protecting workers by absorbing radiation resulting from the nuclear chain reaction. Next an airtight 1/2 inch steel liner surrounds the entire interior of the containment. If the reactor pressure vessel or any of the primal:y piping should break, the escaping steam would be trapped inside the liner. 23
2 1/2 Feet Thick Concrete
- - - 3/8 Inch Steel Liner 41/2 Feet Thick Concrete 185 Feet 122 Feet 1-li..,C1------- 126 Feet - - - - - - -
Figure 13. Containment Schematic ' I Finally, the building's reinforced concrete outer wall is 4 1/2 feet thick tapering to 2 1/2 feet at the top of the dome. It is designed to act as shielding and is also intended to withstand natural and man-made events like earthquakes and even the direct impact from a large commercial jet aircraft. operating the Reactor Safely Accidents The most serious accident that could happen in a nuclear power plant involves overheating in the nuclear reactor core. Such an accident would result from a loss-of-coolant accident or LOCA. During a LOCA, primary coolant would no longer circulate through the reactor core to remove heat. Circulation could be lost if a combination of pipes burst, for example. Conceivably, a chy, overheated reactor core could melt through the pressure vessel. 24
The reactor itself is designed to respond automatically to such an emergency. Operators are also trained to make corrections for any system failure. The automatic and operator responses have two goals: to prevent damage to the reactor, and prevent the release of radiation. Shutting the reactor down is relatively easy. Control rods drop in and chemical to stop the nuclear reaction are injected into the coolant. Losing the coolant itself tends to stop the chain reaction because the coolant is needed to keep the nuclear chain reaction going. Within 10 seconds of shutdown, the amount of heat is less than 5 percent of the amount produced at full power and within 15 minutes, less than 1 percent. To carry heat away during an accident, all reactors have Emergency Core Cooling Systems (ECCS). The ECCS consists of primary and back-up pumps and reservoirs of coolant that operate separately from those that nonnally circulate through the system A nuclear reactor has many different back-up safety systems designed so that if one fails another is always available. Workers There are many different jobs at a nuclear power plant and they are.filled bypeoplewith diverse backgrounds. All employees are initially trained and then retrained annually by the company. Virginia Power's Training centers are fully accredited by the National Academy for Nuclear Training and the Institute for Nuclear Power Operations. The operators are tested and certified by the United States Nuclear Regulatory Commission (NRC). Safety Statistics Job safety is another measure of assurance that the station is being properly operated. Surry Power Station attained 1,000,000 man hours without a lost time accident and is continuing that record into 1992, while North Anna reached 6,000,000 man hours without a lost time accident. Summary
- Nuclear energy provides an alternate source of energy which is readily available. The operation of a nuclear power station has a very small impact on the environment.
- Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. Mankind has always lived with radiation and always will. Radioactivity exists naturally in the soil, water, air and space. All these common sources of radiation contribute to the natural background radiation to which we are exposed.
- In addition to naturally occurring radiation and radioactivity, people are also exposed to man-made radiation. Very small doses result from the production of nuclear power.
- Nuclear power plants are designed to prevent the escape of radiation and radioactive substances.
- A nuclear reactor has many different back-up safety systems designed so that if one fails another is available.
25
IIL Sampang AndAnafysis Program A Sampling Program
- 1. Table 1 summarizes the sampling program for Surry Power Station during 1991.
- The symbols on this table refer to the sample locations shown on Figures 1 through 5. Sample locations are color coded to designate sample type.
- 2. For routine 11.D measurements, two dosimeters made of CaS04:Dy in a teflon card are deployed at each sampling location. Several Tills are co-located with NRC and Commonwealth of Virginia direct radiation recording devices. These are indicted as "co-location" samples.
- 3. In addition to the Radiological Environmental Monitoring Program required by Surry Technical Specifications, Virginia Electric and Power Company splits samples with the Commonwealth of Virginia. All samples listed in Table 1 are collected by Vepco personnel except for those labeled state split All samples are shipped to Teledyne Isotopes in Westwood, New Jersey.
- 4. All samples listed in Table 1 are taken at indicator locations except those labeled "control".*
26
Table2 (Pagel of2) e Surry-1991 Radiological, Sampling Station Dista,u:e And Direction From Unit No. 1 Distance Collection Sample Media Locatl.on Station Miles Din:ctlon Degrees Frequency Remarks Environmental Control (00) Quarterly Onsite' (TID's) West North West (02) 0.17 WNW 29'1!' Quarterly Site Boundary Suny Station Discharge (03) 0.6 NW 309" Quarterly Site Boundary North North West coo 0.4 NNW 330" Quarterly Site Boundary North (05) 0.33 N 357" Quarterly Site Boundary North North East (06) 0.28 NNE 22° Quarterly Site Boundary North F.a.st (OT) 0.31 NE 45° Quarterly Site Boundary East North F.a.st (08) 0.43 ENE 650 Quarterly Site Boundary East (Exclusion) (09) 0.31 E 900 Quarterly Onsite West 00) OAO w '/JO" Quarterly Site Boundary West South West 01) 0.45 WSW 250" Quarterly Site Boundary South West (12) 0.30 SW 225° Quarterly Site Boundary South South West 03) 0.43 SSW 203° Quarterly Site Boundary South (14) 0.48 s 180" Quarterly Site Boundary South South East (15) 0.74 SSE 157" Quarterly Site Boundary South F.a.st 06) 1.00 SE 135° Quarterly Site Boundary F.ast (11) 0.57 E 900 Quarterly Site Boundary Station Intake (18) 1.23 ESE 113° Quarterly Site Boundary Hog Island Reserve 09) 1.94 NNE 260 Quarterly Near Resident, co-location Bacons Castle (20) 4.45 SSW 20'1!' Quarterly Apx. 5 mile no co-location Route 633 (21) 3.5 SW 224° Quarterly Apx. 5 mile 1LD Alliance (22) 5.1 WSW 248° Quarterly Apx. 5 mile 1LD co-location Suny (23) 8.0 WSW 250" Quarterly Population c.enter w Apx. 5 mile no e Route 636 and 637 (24) 4.0 '/JO" Quarterly Scotland Wharf (25) 5.0 WNW 285° Quarterly Apx. 5 mile 1LD co-location Jamestown (26) 6.3 NW 310" Quarterly Apx. 5 mile no co-location Qilonial Parkway (21) 3.7 NNW 330" Quarterly Apx. 5 mile 1LD Route 617 and 618 (28) 5.2 NNW 340" Quarterly Apx. 5 mile no Kingsmill (29) 4.8 N 'J!' Quarterly Apx. 5 mile no Williamsburg (30) 7.8 N O" Quarterly Population c.enter co-location Kingsmill North (31) 5.6 NNE 14° Quarterly Apx. 5 mile 1LD Budweiser (32) 5.7 NNE 27° Quarterly Population Center Water Plant (33) 4.8 NE 41° Quarterly Apx. 5 mile no Dow (34) 5.1 ENE 70° Quarterly Apx. 5 mile 1LD Lee Hall (35) 7.1 ENE 730 Quarterly Population Ceruer co-location Goose Island (36) 5.0 E sso Quarterly Apx. 5 mile 1LD Fort Eustis (31) 4.8 ESE 107" Quarterly Apx. 5 mile 1LD co-location Newport News (38) 16.5 ESE 10'1!' Quarterly Population Ceruer Air Charcoal Suny Station (SS) .37 NNE 15° Weekly Site boundary location with and Particulate Hog Island Reserve (HIR) 2.0 NNE 26° Weekly Co-location Bacons Castle (BC) 4.5 SSW 20'1!' Weekly D Alliance (ALL) 5.1 WSW 248° Weekly Co-location C.Olonial Parkway (CP) 3.7 NNW 330" Weekly Dow Chemical (DOW) 5.1 ENE 70° Weekly Fort F.ustis cm 4.8 ESE 107" Weekly Newport News (NN) 16.5 ESE 12'1!' Weekly Control Location River Water &urry Discharge 0.17 NW 325° Monthly State Split Scotland Wharf 5.0 WNW 285° Monthly Control Location/State Split w Suny Station Intake 1.9 ESE 770 Bi-monlhly Hog Island Point 2.4 NE 52° Bi-monlhly Newport News 12.0 SE 140" Bi-monlhly Chickahominy River 11.2 WNW 300" Bi-monthly Control Location Suny Station Discharge 0.17 NW 325° Monthly Scotland Wharf 5.0 WNW 285° Monthly
' no stored in a lead shield in environmental building e
27
Table2 (Page2of2) Surry-1991 Radiological, Sampling Station Distance And Direction From Unit No. 1 Distance Colledlon Sample Media Location Miles Dlrectfon Degrees Fn:quency Remarks Well Water Surry Station Quarterly Omite' Hog Island Reserve 2.0 NNE Tl° Quarterly w Bacons Castle 4.5 SSW 203° Quarterly Jamestown 6.3 NW 309' Quarterly Shoreline Hog Island Reserve 0.8 N 50 Semi-Annually Sediment Burwell's Bay 7.76 SSE 167" Semi-Annually SD Silt Chickahominy River 11.2 WNW 300" Semi-Annually Control Location Surry Station Intake 1.9 FSE 77° Semi-Annually s Hog Island Point Point of Shoals 2.4 NE 52° Semi-Annually 6.4 SSE 157" Semi-Annually Newport News 12.0 SE 140" Semi-Annually Surry Station Discharge 0.5 NNW 341° Semi-Annually Milk Lee Hall 7.1 ENE 640 Monthly State Split ... EpP5 Colonial Parkway Judkins 4.8 3.7 6.2 SSW NNW SSW 201° 337" 211° Monthly Monthly Monthly State Split Williams 22.5 s 182" Monthly Con1rol Location Oysters Deep Water Shoals 3.9 FSE 105° Bi-Monthly Point of Shoals 6.4 SSE 157" Bi-Monthly 0 Rock Landing Shoals 7.8 SE 140" Bi-Monthly State Split Newport News 12.0 SE 140" Bi-Monthly Clams Chickahominy River 11.2 WNW 300" -Bi-Monthly Con1rol Location Surry Station Discharge 1.3 NNW 341° Bi-Monthly State Split C Hog Island Point 2.4 NE 52° Bi-Monthly Jamestown 5.1 WNW 300" Bi-Monthly Lawnes Creek 2.4 SE 131° Bi-Monthly Crabs Surry Station Discharge 0.6 NW 312" Annually CR Fish Surry Station Discharge 0.6 NW 312" Semi-Annually F Crops Brock's Farm 3.8 s 188" Annually State Split (Com,Peanuts) Slade's Farm 2.4 s 177° Annually State Split Soybeans) (Cabbage,Kale) Pool's Garden 2.3 s 182" Annually State Split Carter's Grove Garden 4.8 NE 560 Annually State Split Ryan's Garden Annually State Split/Control Loe. (Chester, Va.) Stone's Garden Annually State Split Luca's Garden (a) Annually State Splir/Conlrol Loe. (Chester; Va.) Well water sample taken onsile at Surry Fnvironmerual Building (a) Luca's Garden replaced Ryan's Garden on 10/22/91 as control station for vegetation 28
ESE SW Legend Air Sampling Stations TLDSampling State Environmental A, Monitoring Sites
- State TLD Sites
- - - -
- Site Boundary Figure 14. Surry Radiological Monitoring Locations
ws Surry Emergency Plan Map e Air Sampling Stations
-TLD Sampling e Nearest Garden Original© 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA22312USED WITH PERMISSION. No other reproduction
_ _ --~~ be made without the written permission of ADC.
- Surry Emergency Plan Map
-Air Sampling Stations e Nearest Residents ~{j:- -TLD Sampling 41 Nearest Farm Animals e Nearest Garden ,Aquatic Samples
Surry Emergency Plan Map -Air Sampling Stations Nearest Residents ftTLD Sampling e Nearest Farm Animals 4I Nearest Garden Aquatic Samples
Surry Emergency Plan Map
-Air Sampling Stations e Nearest Residents
-TLD Sampling e Nea~est Farm Animals tit Nearest Garden Aquatic Samples Original© 1991 by ADC of Alexandria, Inc., 6440 General Green Way, Alexandria, VA22312USED WITH PERMISSION. No other reproduction
_,./ may be made without the written permission of ADC. ,:£'.\._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ - - - - -
B. Analysis Program
- 1. Table 3 summarizes the analysis program conducted by Teledyne Isotopes for Suny Power Station during 1991.
Table3 (Pagel of3) Surry Power Station Sample Analysis Program Sample Media Frequency Analysis llD(l) Report Units Thermohuninescent Quarterly Gamma Dose 1.5 mR/month Dosimetry (TID) Air Iodine Weekly I-131 0.07 pCVm3 Air Particu1ate Weekly Gros.5 Beta O.ol pCVm3 Quarterly (2) Gamma Isotopic pCVm3 Cs-134 0.05 Q.-137 O.o6 River Water Quarterly Tritium 2000 pCVI composite of monthly sample Monthly and I-131 10 pCVI Bi-monthly Gamma Isotopic Mn-54 15 Fe-59 30 Co-58, 6o 15 Zn-65 30 Zr-95 30 Nb-95 15 Q.-134 15 Cs-137 18 Ba-140 6o La-140 15 Well Water Quarterly Tritium 2000 pCVI I-131 1 Gamma Isotopic Mn-54 15 Fe-59 30 Co-58,6o 15 Zn-65 30 Zr-95 30 Nb-95 15 Q.-134 15 Cs-137 18 e Ba-140 La-140 6o 15 34
Table 3 (amt) (Page2of3) Suny Power Station Sample Analysis Program Sample Media Frequency Analysis llD{l) Report Units Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg-dry Oi-134 150 Oi-137 180 Silt Semi-Annual Gamma Isotopic pCi/kg-dry Oi-134 150 Oi-137 180 Mille Monthly 1-131 1 pCi/1 Gamma Isotopic Oi-134 15 Oi-137 18 Ba-140 6o La-140 15 Oyster Bi-Monthly Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 26o Co-58, 6o 130 Zn-65 26o Oi-134 130 Oi-137 150 Clams Bi-Monthly Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 26o Co-58, 6o 130 Zn-65 26o Oi-134 130 Oi-137 150 Crabs Annually Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 26o Co-58, 6o 130 Zn-65 26o Oi-134 130 Oi-137 150 35
Table3 (Omt.) (Page3of3) Surry Power Station Sample Analysis Program Sample Media Frequency Analysis W>(t) Report Units Fish Semi-Annual Ganuna Isotopic pCi/kg-wet Mn-54 130 Fe-59 26o Co-58, tiO 130 Zn-65 26o C&-134 130 C&-137 150 Crops Annually Ganuna Isotopic pCi/kg-wet 1-131 6o G<;-134 6o G<;-137 80 Footnotes: This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, toether with the aboe nuclides, shall also be identified and reported. (1) LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the Surry Radiological Environmental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed (2) Quarterly composites of each location's weekly air particulate samples are analyzed for gamma emitters. 36
IIL Program Exceptions The REMP program exceptions for 1991 are presented in this section These program exceptions pertain to the samples not obtained or llDs not met during 1991. The REMP deviations are provided in the data tables. For the week of April 2, 1991 through April 9, 1991 the air particulate and charcoal cartridge samples were not obtained for the Colonial Parkway sampling station. The sampler was operating satisfactorily at the beginning of the sampling period. At the end of the sampling period, the sample pump was operating, however the flowmeter and vacuum gauge did riot register any indication. In addition, no sample pump suction was felt by the technician when the sampler inlet was covered. The particulate filter was examined and no sample loading was evident as the filter was still white in color. Based upon this data, it was concluded that the samples were not collected during this timeframe. The sampler was returned to the power station and repaired. For the week of April 16, 1991 through April 23, 1991 the air iodine lower limit of detection (LLD) was not met for the Colonial Parkway sampling station. The fuse on the power pole had blown during the sampling period and 125m3 of air was sampled as compared to an average of 530m3 of air sampled. Although 125m3 of sample is adequate to comply with NRC required LLDs, the analysis performed by Teledyne Isotopes was insufficient to achieve the required LLD. As the result of this occurrence, the manager of the Environmental Analysis Department has been reviewing the air volumes within a week of arrival at Teledyne Isotopes. If a low volume sample arrives it will be counted immediately by gamma ray spectroscopy and if the LLD is not met it will be analyzed promptly by the radiochemical procedure which is a more sensitive analysis. 37
Due to a microorganism infestation in the lower James River (MSX!Dermo), oyster shell stock has been virtually depleted at the Newport News (Naseway Shoal) sample location. Sampling terminated at this location in 1988 and will recommence when the oyster beds revitalize as detennined by the Commonwealth of Virginia. An alternative sampling location at Rock Landing Shoals was selected. Table4 REMP Exceptions For Scheduled Sampling And.Analysis During 1991 - Surry Location Description Date Of Sampling - Reason(s)forLo~/Exception Sta-CP Air Particulates 04/02/91-04/09/91 Air sampler malfunctioned. Sta-CP Air Iodine 04/16/91-04/23/91 LID was not met. Teledyne analysis unable to achieve required LID for air iodine sample which was obtained under low volume conditions. 38
V. Summary And Discussion - 1991 Analytical Results Definitions Below are listed definitions of words and phrases for some of the common terms used in the following sections. Average Activity: The arithmetic mean of detected radioactivity for all samples within a sampled parameter. Impact.: Defines the influence on people. Isotope: The radioactive element identified in a sampled pathway. Lower Lima ofDetection (UD): The smallest amount of radioactivity that can be detected by analysis instrumentation and is statistically significant above background level. The NRC provides Surry Power Station with llD's that we must achieve using our analysis equipment. Many times the results of an analysis is reported as below LID and this may sound like a contradiction. However, the LLD being referred to is the Technical Specification (NRC required) LLD and not the actual instrument LLD. The technology in the analytical field is advancing rapidly and the LLD's achieved by current state-of-the-art equipm!=!nt is in many cases lower values than those required by the NRC. Pathway: Routes by which people may become exposed to man made and naturally occurring radioactivity. In this report, VEPCO and the State of Virginia sample and analyze components of many pathways; for example: air samples are obtained to analyze the exposure through the inhalation pathway and fish and other marine species are analyzed for exposure through the ingestion pathway. Reporting Level Concentration: A method of referencing the measured railionuclide concentrations in sample media to a dose consequence. Reporting level concentrations are listed in the NRC Regulatory Guide 4.8. These concentrations are based upon 25% of the annual dose commitment required by 10CFR50, Appendix I, to meet the criterion "As Low As Reasonably Achievable". Trend: Steady, rising or falling based on the same sampled parameter from preoperational data and previous years. 39
* * ' ,, ~ I S I ,
- ~<* ;: : I ~ ~~ ,J" ;.; 'JL 1
*, ~) ,> ,. ~.-.~~J;u:~~1-J~L v* '1~i1.,,,i..::,:.,. ~1,,:~~-0}t~*~ti;.::*t,~'j:~),/,\I_~,. -'-.::~~~i/tfb~:**1~':~i:1:Ji1~&iiti~,~l~\,,~~i~*i~ti~~-ii~~~Jt?fr~
Analytical Resu"/ts 1991 Analytical resultes are discussed by pathway below. Airborne Exposure Pathway Airborne Radioiodine Charcoal cartridges are used to collect airborne raclioiodine. Once a week, the samples are collected and analyzed. The results are presented in Table B-1. All results are below the lower limit of detection with no positive activity detected. These results are similar to preoperational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl. Airborne Gross Beta Results of the weekly gross beta analysis are presented in Table B-2. A review of Table B-2 indicates that results from the station indicator compare favorably to the control
- location in Newport News; briefly summarized in Table 5.
Table5 Gross Beta Analysis Summary Quarterly Average Quarterly Average Calendar Quarter All Locations Control Station 1st 16 pCifm3 15 pCi/m3 2nd 14 pCi/m3 14 pCi/m3 3rd 18 pCifm3 17 pCi/m3 4th 19 pCifm3 17 pCi/m3 Quarterly averages are consistent with background radioactivity levels. The gross beta concentrations observed indicate a steady trend compared to levels found during the previous 6 years. Gross beta activity found during the preoperational and early operating period of Sunywere higher because of nuclear weapons testing. During the past two decades nearly 740 nuclear weapons have been tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident, airborne gross beta results have trended at stable levels . 40
Airborne Gamma Isotopic
- Air particulate filters are analyzed for isotopes that are gamma emitters. The results of the composite analysis are listed in Table B-3. No gamma emitting radioactivity attributable to the power station was detected. However, natural background radioactivity was detected in many of the samples.
The two isotopes that were identified are beryllium-7 and potassium-40. Beryllium-7 is continuously produced in the upper atmosphere by cosmic radiation. Potassium-40 is naturally present in foods, building materials and soil. 1.0E+O - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , b=~-
...2:-
- , 1.0E-1 (a)
(/) I 0 0 a.
~
(')' E 0
- a. 1.0E-2 1.0E-3 _.._--.----....-----..------r-------.-----,.-----,-----,----
1984 1985 1986 1987 1988 1989 1990 1991 1992 (a) Chernobyl ...... Indicator _._ Control -~" Avg-Pre Op -+* Avg-LLD Trending Graph - 1: Gross Beta In Air Particulates 41
Waterborne Exposure Pathway River Water The analysis results for the James River water sam-pling program are presented in Table B-4. Samples of James River water are collected as monthly grab samples at both Suny Discharge and Scotland Wharf and Bi-monthly grab samples at Hog Island Point, Newport News, Chickahominy River and Suny Intake. All samples are analyzed by gamma spectroscopy and for iodine-131 by a radiochemical procedure. These samples are also composited and analyzed for tritium and on a quarterly basis. Naturally occurring potassium-40 was measured in 12 samples with an average concentration of 116.0 pCi/liter. All samples were analyzed for gamma emitting radioisotopes. Two samples collected at the Suny Discharge station had an average cesium-137 activity of 21.6 pCi/liter. The average of these cesium samples is slightly above the required LLD for river water samples. With the exception of naturally occurring potassium-40 and the two cesium-137 results, no other gamma emitters were detected. In particular, no iodine-131 was detected. This trend is consistent with previous years. Tritium was measured in 8 of 24 quarterly composite samples. The average tritium concentration was 548 pCi/liter. Preoperational data for tritium indicated levels of activity considerably higher than current levels due in part to atmospheric weapons testing. This years level is less than the average for the past 6 years. The State of Virginia samples water from the station discharge and a control site located up stream of the station Scotland Wharf. These samples are taken as part of the State Split Sample Program and analyzed independently. The results are presented in Table B-5. River water from the station discharge and control location identified tritium concentration of 707 pCi/liter and 810 pCi/liter respectively. Scotland Wharf is taken as a weekly grab sample. Station discharge is sampled by a composite sampler and collected weekly. Monthly composite samples are prepared for gamma and iodine-131 analysis and quarterly composites are prepared for tritium analysis. In addition to the VEPCO monthly grab sample and the State Split composite sample, a VEPCO station discharge composite sampler was placed in service in May of 1989. A tritium composite from this samplerwas analyzed monthly and then composited for quarterly analysis. The average tritium concentration for 1991 was 725 pCi/liter. 42
100000
- en
~
...C' 0
0 a. 10000
-~s (I)
(.)
- a. 1000 100 +---.--..---.---,,-..---.---,--..--.....----.-................----.--,--"""T"-r---.----.--,---.-----.--,--..---i 68 70 72 74 76 78 80 82 84 86 88 90
-a- Surry Discharge ..._ Scotland Wharf *+, Average LLD Trending Graph 2: Tritium In River Water O
The attached trend graphs provide a comparison of tritium concentration measured in the downstream sample (Surry Station Discharge) and in the upstream control location (Scotland Wharf). As expected, the Surry discharge samples indicated higher levels of tritium than the control location. The water in the discharge canal is further diluted by the river water beyond the discharge structure. The average tritium concentration in grab samples taken downstream of the station indicate good comparison to the State Split control concentration. Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry does monitor well water and analyzes water samples from four indicator locations. The results of these sample analysis are presented in Table B-6. These samples were analyzed by gamma spectroscopy and indicated that there were no man made or naturally occurring radioisotopes present. Preoperational samples were only analyzed for gross alpha and gross beta. Gamma emi~g isotopes have not been detected within the recent past and this trend is consistent throughout the operational monitoring program. All well water samples were analyzed for tritium. No tritium was detected in any of the control or indicator samples. Preoperational samples were not analyzed for tritium however, this years results indicate a decrease from previous operating data. 43
,*~',:.1: \~~*', >'.'~~~. :*;.,~*. ~-,:;:i~,"'~;,~*:~.L;:i:~;... i . 1'.~'.h ,\:~ ~ ~' c 1,\'-':~*.': \:~**~ '~ :.(_', ' ~ *.. '1 **', '
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() a. 10 1 -+--..--.--.......---,.--,-...,...........,....--,,-......-.---.--..--........-,---,.-...,......-,---.-.......................- . . -.........--t 1/86 7/86 1/87 7/87 1/88 7/88 1/89 7/89 1/90 7/90 1/91 7/91
-&i- Station - BC ...._. Station - HIR -b.. Station - JMTN _._Station - SS -+-Average LLD Trending Graph - 3: Tritium In Well Water Aquatic Exposure Pathway Silt Silt samples were taken to evaluate any buildup of radionuclides in the environment due to the operation of the power station. The radioactivity in silt is a result of precipitation of radionuclides in the waste discharges and the subsequent dispersion ofthe material by the river current. Sampling this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in clams, oysters and fish.
Silt samples are collected from six locations both up stream and down stream of the power station. These samples are analyzed for gamma emitting radioisotopes. The results of these analyses are presented in Table B-7. The NRC does not assign reporting levels to radioisotopes measured in this pathway. Surry's operating license requires that we track and trend the concentrations of man made and naturally occurring gamma emitters. Preoperational analyses indicates that there were no man made radioisotopes present in this pathway. 44
1000
~
(/) 0 u a. 100 ~
....Q)'
~ s () a. 10 72 74 76 78 80 82 84 86 88 90
--M- Hog Island ...., Station Intake ~*** Station Discharge 0
+-* Average LLD During the preoperational period cobalt-SB was not measured.
Trending Graph - 4: Cobalt-58 In Silt 1000
....2-CJ) 0' 100
() a. ~
....Q)'
~ s 10 () a. 1 4--..----.---.--...----.-....---......-....--..----......--....---.---.....-~----~ 72 74 76 78 80 82 84 86 88 90
-II- Hog Island ...,. Station Intake ** Station Discharge *+*, Average LLD During the preoperational period cobalt-60 was not measured.
Trending Graph - 5: Cobalt-60 In Silt 45
10000
- ...~
CJ) I 1000 0 0
- 0. 100
~
I (I) s () 0. 10 72 74 76 78 80 82 84 86 88 90
-II- Hog Island .... Station Intake ~¥ Station Discharge *+* Average LLD During the preoperational period cesium-134 was not measured.
Trending Graph - 6: Cesium-134 In Silt
~
CJ) g_ 1000
~
I (I)
-~
s () 0.
~--*--*--*-------**----*-*****--**-**-*--*-***---*-***-*--*-**-*-*-**-****-*****--*--------------*
72 74 76 78 80 82 84 86 88 90
...._ Hog Island ..._ Station Intake ** Station Discharge *+* Average LLD During the preoperational period cesium-137 was not measured.
Trending Graph - 7: Cesium-137 In Silt 46
Cobalt-58, cobalt-60, cesium-134 and cesium-137 average levels indicate a decrease in concentration when compared to last year and the previous 5 year trend. The concentration of manmade radioisotopes in silt is projected to decrease. Surry Power Station has recently put into service a Radioactive Waste Treatment Facility which employs state of the art technologies to reduce the volume and activity of liquid effluents and reduce the impact on the environment. This facility went into operation in September of 1991. Shorellne Sediment Unlike river bottom silt, shoreline sediment may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. Samples were taken in February and August at Hog Island Point and at Burwell's Bay. The samples were analyzed by gamma spectroscopy and the results are presented in Table B-8. This exposure pathway was not selected for analysis during the preoperational years. Nevertheless, samples analyzed over the past 6 years from this pathway indicate a decreasing trend in the detection of gamma radioisotopes. This years analysis along with last years results indicates that no radioisotopes attributable to the operation of the power station have been detected. Naturally occurring radioisotopes were measured in several of the samples. Potassium-40, thorium-228 and radium-226 show a steady trend over the recent past. Ingestion Exposure Pathway Mllk Milk samples are an important indicator for measuring the affect of radioactive iodine, and other radioisotopes in airborne releases. The dose consequence to man is from both a direct and indirect exposure pathway. The direct exposure pathway is from the inhalation of radioactive material. The indirect exposure pathway is from the grass-cow-milk pathway. In this pathway radioactive material is deposited on the plants consumed by the dairy animals. The radioactive material is in tum passed on to man via the milk. The results of iodine-131 and other gamma analysis of milk are presented in Table B-9. Iodine-131 has not been detected in milk prior to and since the 1986 accident at Chernobyl in the Soviet Union. Preoperational data shows that cesium-137 was detected in this pathway. The average activity over the past six years is consistent with the preoperational data. The previous two years shows a significant decline in cesium-137 as none was detected. Naturally occurring potassium-40 was detected in all samples analyzed. The preoperational monitoring program did not analyze for this radioisotope. 47
Strontium-90 was detected in 9 of the 12 samples collected in participation with the State Split Program. Preoperational data shows levels 5 to 6 times higher than present values. This years analysis show a decrease when compared to the previous two years and is less than the average for the past 6 years. Strontium-90 is not a part of station effluents but rather a product of weapons fallout. - Aquatic Biota All plants and animals have the ability to concentrate certain chemicals. Radioisotopes display the same chemical properties as their non-radioactive counter part. VEPCO samples various aquatic biota to determine the accumulation of radioisotopes in the environment. The results of the sampling program for this pathway are detaile~ below. Clams were analyzed from 5 different locations. The results of the analysis is presented in Table B-10. As expected, naturally occurring potassium-40 was detected in 14 of 30 samples. Potassium-40 is a naturally occurring radioisotope and is not a component of station effluent. Cesium-137 was detected in one sample from the Station Discharge. The concentration was 24.9 pCi/kg. This activity equates to 1.2% of the reporting levels for radioactivity concentrations in environmental samples. No other gamma emitting radioisotopes were detected. The trend of gamma emitting radioisotopes in clams over the recent past continues to decrease and is well below the lower limits of detection with the one exception discussed above. This marked decrease coincides with the extensive steam generator replacement project completed in 1982. Oysters were analyzed from 3 different locations. The results of the analysis is presented in Table B-11. As expected, naturally occurring potassium-40 was detected in 23 of 24 samples. The current average level of potassium-40 is comparable to the preoperational average. No gamma emitting radioisotopes were detected in any samples. This is consistent with preoperational data and data collected since the 1986 accident at Chernobyl in the Soviet Union. Crab samples were collected inJune from the discharge canal of the station and analyzed by gamma spectroscopy. The results of this analysis is presented in Table B-12. As expected naturally occurring potassium-40 was detected. Potassium-40 is a naturally occurring radioisotope and is not a component of station effluent. No other gamma emitting radioisotopes were detected in this sample. This is consistent with preoperational data and data collected during the past 6 years. 48
100
~y-..g.:....:m*=-dfill.***-li ~ U 00 0000 0 0 0
- 0 0
- 0 o
- 0 0 0 Oa 000 00 0 000 H a HOO O O O O o O
- 0 00.
8 a. ~ 10 1 -+--..---,---.----,,---.---,---r--..---,----,---,,---,---.---,--"T""--r---r----1 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91
-a- Chickahominy -+- Surry Discharge n Hog Island *+- Average LLD During the preoperational period cobalt-58 was not measured.
Trending Graph - 8: Cobalt-58 In Clams
...c:'
- , 100 en 0'
(.) a. ~ Cl s ()
- a. 10 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91
-II- Chickahominy -+- Surry Discharge *-k Hog Island *+- Average LLD During the preoperational period cobalt-60 was not measured.
Trending Graph* 9: Cobalt-60 In Clams 49
- 100 I
8.
~
I
~
0 10 a. 1---.------.....--.-----,..-....---...------.----~-----.----~---.-- 74 76 78 80 82 84 86 88 90
-n- Chickahominy _.. Surry Discharge *'1::::-* Hog Island *+* Average LLD Trending Graph - 10: Cesium-137 In Clams Four fish samples were collected in April and October from the station discharge canal and analyzed by gamma spectroscopy. The results of this analysis is presented in Table B-13. As expected naturally occurring potassium-40 was detected in all samples. Based on the previous 6 years, the trend of potassium-40 in fish sho~s a slight increase.
Cesium-137 was not obseIVed in any of the fish samples. The trend in cesium-137 in fish shows a decrease when compared to the previous 6 years as none was detected in any sample. 50
Food Products and Vegetation Food products and vegetation samples were collected from six different locations and analyzed by gamma spec-troscopy. The results of this analysis is presented in Table B-14. As expected naturally occurring potassium-40 was detected in all samples. The average concentration was lower than the average in 1990. Potassium-40 is a naturally occurring radioisotope and is not a component of station effluent. Naturally occurring beryllium-7 was detected in one of the ten samples. Cesium-137 was measured in one cabbage sample with an activity of 10.0 pCi/kg. This measurement is less than the average concentration over the past 6 years and indicates a decreasing trend. This sample is less than the lower limits of detection (80 pCi/kg) and is 0.5% of the required reporting limits. mrect Radiation *. ': ~ .. . Exposure Pathway * . '-,_'*,* ':.:_'.._s._'*\*.*.,
. .: .. *..,._ ... ~ .
' I \';
A thermoluminescent dosimeter (TID) is an inorganic crystal used to detect ambient radiation. TIDs are placed in two concentric rings around the station; one at the site boundary and the other at approximately 5 miles from the station. TIDs are also placed in special interest areas such as population areas and nearby residents. Several addi-tional TIDs serve as controls and these TIDs measure ambient radiation. Ambient radiation comes from natu-rally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station. The results of this analysis is presented in Table B-15 and B-16. Control and indicator averages indicate a continuing decreasing trend in ambient radiation levels. This years levels are slightly less than the previous six years. 51
100
- ~
(I) 0 u C. j
.c 'E 10 0 ~ "E (1J "O
C (1J a: E 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991
..._ Site Boundary .._ 5 Mile Boundary Trending Graph - 11: Direct Radiation Measurements - TLD Results
- 52
VL Conclusions The results of the 1991 Radiological Environmental Monitoring Program for Surry Nuclear Power Station have been presented The following sections present conclusions for each pathway individually followed by a program summary. Airborne Exposure Pathway Air particulate gross beta concentrations of all the indicator locations for 1991 trend well with the control location. The gross beta concentrations indicate a steady trend when compared to the levels found during the previous 5 years. Gamma isotopic analysis of the particulate samples identified natural background radioactivity. No radioactivity attributable to the operation of the power station was identified. Waterborne Exposure Pathway All river water samples were analyzed for gamma emitting radioisotopes. With the exception of naturally occurring potassium-40 and two detections of cesium-137 from the Station Discharge,* no other gamma emitters were detected. In particular, no iodine-131 was detected. Tritium activity was measured in several river water samples with an average concentration of 548 pCVliter. This value is less than the average for the past five years. The percent of Technical Specification Reporting Level is 1.83% of the VEPCO Reporting Level Concentration. Because there is no supply of drinking water or water used for crop inrrigation, there is an insignificant dose consequence to the public from this pathway. Research of the preoperational data for tritium indicates levels of activity considerably higher than current levels due to atmospheric weapons testing. Well water samples were analyzed and indicated that there were no man made or naturally occurring radioisotopes present Aquatic Exposure Pathway The NRC does not assign reporting levels to radioisotopes measured in silt samples. The average levels of man-made radioisotopes in silt indicate a decreased concentration when compared to the previous five year trend. In September 1991 Surry Power Station put into service a Radioactive Waste Treatment facility which is expected to reduce the volume and activity of liquid effluents released to the environment. Shoreline sediment sample analysis detected only naturally occurring radioisotopes at concentrations equivalent to normal background activities. No radioisotopes attributable to the power station operation were found in any sediment sample. 53
Ingestion Exposure Pathway Milk samples are an important indicator for measuring the affect of radioactive iocllne and radioisotopes in airborne releases. Iodine-131 was not measured in any of the 60 milk samples. Naturally occurring potassium-40 was detected at a slight decrease in average concentration when compared to the previous two years. The strontium-90 concentration in this years analysis shows a decrease when compared to the previous two years. Strontium-90 is not a part of station effluent, but rather a product of weapons fallout. As expected, naturally occurring potassium-40 was detected in all clam, oyster, and crab samples. No gamma emitting radioisotopes were detected in any of the samples. Cesium-137 was detected in one clam sample. Compared to previous years, Cesium-137 detections are showing a declining trend. Analysis of all fish samples detected naturally occurring potassium-40 as expected. Cesium-137 was not obsetved in any fish samples during 1991, nor were any other gamma emitting radioisotopes detected in any of the samples. This compares favorably with the detection of cesium-137 during 1990 in one fish samples. As expected, naturally occurring potassium-40 and beryllium-7 (one sample) was detected in
- food product and vegitation samples that were collected and analyzed. Cesium-137 was obsetved in one cabbage sample. The concentration of radioactivity found in samples this year is comparable to last year and may be attributable to world wide fallout. The percent Technical Specification Reporting Level for this sample is calculated to be less than 1% and indicates an insignificant ingestion dose consequence.
Dl.rect Radiation Exposure Pathway Control and indicator averages indicate a decreasing trend in ambient radiation levels. This years levels are slightly less than the previous five years. The direct radiation exposure that may be attributed to the station operation is 1.0 mR/standard month (0.031 mR/day). This exposure is not significant when compared to the United States average background radiation levels of 360 mRem/year (0.98 mRem/day). 54
Program Conclusions
- Based on the results of the REMP, Surry Power Station is operating within regulatory limits.
- All samples analyzed were either below the reporting limits or below the lower limits of detection.
- Overall, the results were as expected for normal environmental samples. Naturally occurring radioactivity was observed in sample media and was within the expected activity ranges.
- Occasional samples revealed the presence of man-made isotopes. The concentration of isotopes attributable to station effluents are very low and of no significant dose consequence.
55
VIL References
- 1. DOE/NE-0072, "Nuclear Energy and Electricity, The Harnessed Atom," US Dept. of Energy, 1986.
- 2. Eichholz, G., "Environmental Aspects of Nuclear Power," Lewis Publishers, Inc., 1985.
- 3. Eisenbud, M., "Environmental Radioactivity," Academy Press, Inc., Orlando, Fl, 1987.
- 4. Fitzgibbon, W., "Energy Skill Builders, Nuclear Reactor," Enterprise for Education, Inc.,
1987.
- 5. Glasstone, S., and Jordan, W., "Nuclear Power and its Environmental Effects," American Nuclear Society, 1982.
- 6. National Council on Radiation Protection and Measurements, Report No. 39, "Basic Radiation Protection Criteria," Washington, D.C., January 1971.
- 7. National Council on Radiation Protection and Measurements, Report No. 45, "Natural Background Radiation in the United States," Washington, D.C., November 1975.
- 8. National Council on Radiation Protection and Measurements, Report No. 95, "Radiation Exposure of the U.S. Population from Consumer Products and Miscellaneous Sources,"
Washington, D.C., December 1987.
- 9. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," Washington, D.C., December 1987.
- 10. NUREG 0472, "Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.
- 11. United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October, 1977.
- 12. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December, 1975.
- 13. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.
- 14. VEPCO, Station Administrative Procedure, VPAP-2103, Offsite Dose Calculation Manual, Rev 2, September 1, 19)1.
- 15. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.
56
RADIOLOGICAL ENVIRONMENTAL MONOORING PROGRAM
SUMMARY
Surry Nuclear Power Station, Surry County, Virginia - 1991 Docket No. 5-280-281 January 1 to December 31, 1991 Page 1 of 3 All Indicator Control tbl,- Medium or Analysis Locations Location with Hiahest Mean Location laDl9 Pathway Total ...LD1 Repcrad Sampled Type No. Mean -*-. Name ..---* - Mean Mean 11.1...-,-- (Unit) Ranae - Ranae
- Ranae mer1s Air Iodine 1-131 416 0.07 -(0/364) N/A NIA NIA -(0/52) 0 (pCi/m3) - -
Airborne Gross 415 10 16.8(363/363) CP 3.7mi 17.6(51/51) 15.9(52/52) 0 Particulate Beta (5.80-35) NNW (7.5-35) (7.3-25) {1e-03 Gamna 32 0 pCi/m3) Be-7 32 - 110(28/28) ALL 5.1 mi 124(4/4) 109(4/4) 0 (79.6-136) WSW {108-136) (95.6-114) K-40 32 130 6.26(1/28) CP 3.7mi 6.26(1/4) -(0/0) 0
- NNW - -
River Gamna 48 0 Water2 K-40 48 - 108(10/42) CHIC 158(2/6) 158(2/6) 0 (pCi/liter) {66.9-174) (25.9-291) (25.9-291) Cs-137 48 - 21.6(2/42) SD 0.17 mi 21.6(2/12) -(0/6) 0 (14.3-28.9) NW - Tritium 24 2000 597(7/20) SD 0.17 mi 1285(2/12) 200(1/4) 0 (Otrly) (140-2100) NW (470-2100) - River Gamna 24 0 Water3 K-40 24 0 132(5/12) SD 0.17 mi 132(5/12) 71.8(1/12) 0 (pCi/liter- (58.0-347) NW (58.0-347) - State Split) Tritium 24 2000 707(3/4) SW 5.0mi 810(1/4) 810(1/4) 0 (Otrly) (300-1200) WNW - - Well Water Gamna 16 0 (pCi/liter) K-40 16 - -(0/16) N/A NIA NIA NONE 0 Tritium 16 2000 -(0/16) NIA NIA NIA NONE 0 (Otrly) - Silt Gamna 12 0 pCi/kg (dry) Be-7 12 1100(1/10) SI 1.9 mi 1100(1/2) -(0/2) 0
- ESE - -
K-40 12 14535(10/10) CHIC 11.2 mi 16650(2/2) 16650(2/2) 0 (7550-16700) WNW (15100-18200) (15100-18200) Co-58 12 203(2/10) SD 0.5mi 337(1/2) -(0/2) 0 (69.9-337) NNW - - Co-60 12 430(8/10) SD 0.5mi 902(2/2) 142(2/2) 0 (71.1-1000) NNW (804-1000) {113-170) Cs-134 12 150 141 (4/10) SI 1.9 mi 173(1/2) -(0/2) 0 (115-173) ESE - - Cs-137 12 180 692(9/10) SD 0.5mi 1017(2/2) 780(2/2) 0 {164-1150) NNW (883-1150) (663-897)
RADIOLOGIQU ENVIRONMENJ'AL MONITORING PROGRAM
SUMMARY
Surry Nuclear Power Station, Surry County, Virginia - 1991 Docket No. 5-280-281 January 1 to December 31, 1991 Page 2 of 3 All Indicator Control Nan-Medium or Analysis Locations Location with Hicahest Mean Location rwi1B Pathway Sampled (Unit) Type Total No. l.LD1 Mean Rancae Name LJISlilr-Mean Range Mean Rancae
**~*-
Repomd mens Silt Ra-226 12 1994( 1011 0) SD 0.5mi 2550(2/2) 2915(2/2) 0 cont'd (1200-3160) NNW (1940-3160) (2600-3230) pCi/kg (dry) Th-228 12 1121(10/10) CHIC 11.2 mi 1355(2/2) 1355(2/2) 0 (447-1440) WNW (1210-1500) (1210-1500) Shoreline Gamna 4 0 Sediment Spec (pCi/kg dry) K-40 4 3483(414) HIR 0.8mi 5175(2/2) NONE 0 (1770-5830) N (4520-5830) Ra-226 4 554(114) BB 7.76mi 554(112) NONE 0
- SSE -
Th-228 4 213(114) HIR 0.8mi 213(112) NONE 0
- N -
Milk Gamna 60 0 (pCi/liter) K-40 60 - 1282(48148) CP 3.7mi 1325(12/12) 1326(12/12) 0 (1150-1590) NNW (1190-1590) (1170-1540) 1-131 60 1 -(0148) NIA NIA NIA -(0/12) 0 Cs-137 60 -(0148) NIA NIA NIA -(0112) 0 10 - - - Sr-89 12 - -(0112) NIA NIA NIA -(010) 0 Sr-90 12 - 0.82(9112) CP 3.7mi 1.53(314) -(010) 0 (0.16-2.6) NNW (0.38-2.6) - Clams Gamna 30 0 (pCi/kg wet) Spec K-40 - - 412(14124) HIP 2.4 mi 589(316) 289(416) 0 (227-813) NE (419-813) (233-383) Cs-137 30 - 24.9(1130) SD 0.6mi 24.9(116) - 0
- NW -
Oysters Gamna 24 0 (pCi/kg wet) Spec K-40 - - 565(23124) DWS 3.9mi 635(516) NONE 0 (190-1350) ESE (464-891) Crabs Gamna 1 0 (pCi/kg wet) Spec K-40 - - 1390(111) SD 0.6mi 1390(111) NONE 0
- NW -
58
RADIOLOGIDU ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Surry Nuclear Power Station, Surry County, Virginia - 1991 Docket No. 5-280-281 Januazy 1 to December 31, 1991 Page 3 of 3 All Indicator Control Non-Medium or Analvsis Locations Location with Hiahest Mean Location roui18 Pathway Sampled (Unit) Tvpe No. Total
... LD1 Mean Ranae Name -*
LJISliU- Mean Ranae Mean Ranae
**~*-
Rapamd mens Fish Ganma 4 0 (pCi/kg wet) Spec K-40 - - 1968(4/4) SD 0.6mi 1968(4/4) NONE 0 (1840-2150) MN (1840-2150) Direct Ganma 333 2 5.9(317/317) 38 16.5 mi 7.5(8/8) 5.1(16/16) 0 Radiation (4.1-8.5) ESE (6.7-8.3) (3.9-6.4) TLDs(mR/ std. month) Vegetation Ganma 10 0 (pCi/kg wet) K-40 10 7226(8/8) Brock 8190(3/3) 4500(2/2) 0 (2150-15300) Garden (3860-15300) (3760-5240) Be-7 10 107(1/8) Carter 107(1/1) -(0/2) 0
- Garden - -
Cs-137 10 10.0(1/8) Carter 10.0(1/1) -(0/2) 0
- Garden - -
1 LLD is the Lower Llmit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. 2 Analyses for monthly and bi-monthly samples are listed in Table B-4. 3 Monthly State Split analyses presented in Table B-5.
TABLE ~1: IODINE-131 CONCENTRATION IN FILTERED AIR e pCi/m3 Surry Nuclear Power Station, Surry County, Virginia - 1991
+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 2 COLLECTION SIATIOH~
DATE ss HIR BC ALL CP DOW FE NN JANUABY 01 /02/91-01 /08/91 <.02 <.02 <.02 <.02 < .01 < .01 < .01 < .01 01/08/91-01/15/91 <.02 <.02 <.02 <.02 < .01 < .02 < .007 < .01 01/15/91-01/22/91 <.02 <.02 <.02 < .02 <.01 < .01 < .01 < .01 01/22/91-01/29/91 <.02 <.02 <.02 < .02 <.02 <.02 <.02 <.02 EEEJBUABY 01/29/91-02/05/91 < .01 < .01 < .01 < .01 <.02 < .02 < .02 < .02 02/05/91-02/12/91 < .02 <.02 <.02 < .02* < .01 < .01 < .01 < .01 02/12/91-02/19/91 <.02 <.02 <.02 <.02 < .02 <.02 <.02 <.02 02/19/91-02/26/91 <.02 <.02 <.02 < .02 <.02 <.02 <.02 <.02 MABCH 02/26/91-03/05/91 < .02 <.02 < .02 < .02 (a) < .01 < .01 < .01 (a) < .01 03/05/91-03/12/91 < .02 < .02 <.02 <.02 < .01 < .01 < .01 < .01 03/12/91-03/19/91 < .01 < .01 < .01 < .02 (b) < .02 <.02 <.02 < .02 (c) 03/19/91-03/26/91 < .02 <.02 <.02 <.02 < .02 <.02 <.02 <.02 03/26/91-04/02/91 <.01 < .01 < .01 < .01 < .01 < .01 < .01 <.02 e APRIL 04/02/91-04/09/91 04/09/91-04/16/91
.01
.01
< .01
< .01
.009
.01
< .009
<.02 (d)
< .02
< .01
<.02
< .01
<.02
<.02
<.03 04/16/91-04/23/91 < .02 <.02 < .02 < .02 < .09 (e) < .02 <.02 <.02 04/23/91-04/30/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 MAY 04/30/91-05/07/91 < .01 < .01 < .01 < .01 <.05 < .01 < .01 < .01 05/07/91-05/14/91 < .01 < .01 < .01 < .01 < .02 <.02 <.02 <.02 05/14/91-05/21 /91 < .01 < .01 < .01 < .01 < .02 <.02 <.02 <.02 05/21/91-05/28/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 JUNE 05/28/91-06/05/91 < .02 <.02 <.02 < .01 < .02 <.02 <.02 <.02 06/05/91-06/11/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 06/11/91-06/18/91 < .01. < .01 < .01 < .01 < .04 (f) <.02 <.02 <.02 06/18/91-06/25/91 < .02 < .02 <.02 < .02 <.02 <.02 <.02 <.02 06/25/91-07/02/91 < .01 < .01 < .009 < .009 < .01 < .01 < .01 < .01
.J..!.!.LY 07/02/91-07/09/91 < .01 < .02 < .01 < .01 < .02 <.02 < .01 <.02 07/09/91-07/16/91 < .01 < .01 < .01 < .01 <.01 < .01 < .01 < .01 07/16/91-07/23/91 < .02 < .01 < .01 <.02 < .02 < .01 < .01 < .01 07/23/91-07/30/91 < .02 < .02 <.02 < .02 < .02 < .01 < .01 < .01
TABLE ~1: IODINE-131 CONCENTRATION IN FILTERED AIR - pCi/m3 COLLECTION DATE Surry Nuclear Power Station, Surry County, Virginia - 1991
+/- 2 Sigma ss HIR January 1 to December 31, 1991 BC STATIONS ALL CP DOW Page 2 of 2 FE NN AUGUSI 07/30/91-08/06/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 08/06/91-08/13/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 08/13/91-08/20/91 < .01 <.02 < .01 < .01 <.009 < .01 < .009 < .009 08/20/91-08/28/91 < .009 < .009 <.009 < .009 <.02 <.02 <.02 <.02 08/28/91-09/03/91 <.02 <.04 <.02 <.02 <.05 < .02 <.02 <.02 SEeIEMaEB 09/03/91-09/10/91 < .01 < .01 < .01 < .01 <.01 < .01 < .01 < .01 09/10/91-09/17/91 < .01 <.02 < .01 < .01 <.02 < .02 < .01 <.02 09/17/91-09/24/91 < .02 <.02 < .01 < .01 < .01 < .01 < .01 < .009 09/24/91-10/01/91 < .01 < .01 < .01 < .01 < .01 < .01 <.01 < .01 QCIQBEB 10/01/91-10/08/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 1 0/08/91-1 0/15/91 < .02 <.02 < .01 <.02 < .01 < .01 < .01 < .01 10/15/91-10/22/91 < .01 < .01 < .01 < .01 < .01 < .01 < .01 < .01 10/22/91-10/29/91 < .01 < .01 < .01 < .01 < .005 < .01 < .01 < .01 NOVEMBER e 10/29/91-11/05/91 11/05/91-11/12/91 11/12/91-11/19/91
.01
.02
.01
< .009
<.02
< .01
.01
.02
.01
< .01
<.02
< .01
< .01
< .01
<.02
< .01
< .01
< .02
< .01
< .01
<.02
< .01
< .01
<.02 11/19/91-11/26/91 < .02 <.02 < .02 <.02 < .02 <.02 <.02 <.02 DECEMBEB 11 /26/91-12/03/91 < .01 < .01 < .01 < .01 < .02 <.02 <.02 < .02 12/03/91-12/1 0/91 < .01 < .01 < .01 < .01 < .02 <.02 < .02 <.02 12/10/91-12/17/91 <.02 < .01 < .01 < .01 < .02 < .02 <.02 <.02 12/17/91-12/23/91 < .03 <.03 <.03 <.03 <.03 <.03 <.03 <.03 12/23/91-12/30/91 <.02 <.02 < .02 < .02 < .02 <.02 <.02 <.02 (a) Volumes estimated based on start/stop times due to sampler timer malfunction.
(b) Cause for low hours on sampler is unknown. (c) Timer malfunctioned. Volume calculated is based on interval since filter last changed. (d) Air sampler malfunctioned and exact volume unknown. See exemptions page. (e) Blown fuse resulting in low air volume. LLD not met. See exceptions page. (f) Blown fuse on power pole resulting in low air volume. - 61.
TABLE B-2: GROSS BETA CONCENTRATION IN AIR PARllCULATES Surry Nuclear Power Station, Surry County, Virginia - 1991 1.0 e-03 pCifm3 +/- 2 Sigma January 1 to December 31, 1991 Page 1 of 2 SIATIONS COLLECTION ss HIR BC ALL CP DOW FE NN Average DATE +/- 2 SI ma JANUARY 01/02-08/91 20+/- 2 23+/- 2 22+/- 2 24+/- 2 21 +/- 2 21 +/- 2 23+/- 2 21 +/- 2 22+/- 3 01 /08-15/91 9.5 +/- 1.4 10+/- 1 11 +/- 1 13+/- 2 9.5 +/- 1.4 10+/- 1 8.0 +/- 1.3 10+/- 1 10+/- 3 01/15-22/91 13+/- 2 15+/- 2 14+/- 2 15+/- 2 12+/- 2 11 +/- 1 14+/- 2 14+/- 2 14+/- 3 01/22-29/91 19+/- 2 22+/- 2 23+/- 2 25+/- 2 20+/- 2 20+/- 2 22+/- 2 19+/- 2 21 +/- 4 FEBRUARY 01/29-05/91 19+/- 2 20+/- 2 21 +/- 2 20+/- 2 19+/- 2 18+/- 2 22+/- 2 19+/- 2 20+/- 3 02/05-12/91 16+/- 2 16+/- 2 17+/- 2 18+/- 2 18+/- 2 18+/- 2 24+/- 2 16+/- 2 18+/- 5 02/12-19/91 11 +/- 2 14+/- 2 16+/- 2 18+/- 2 13+/- 2 15+/- 2 18+/- 2 16+/- 2 15+/- 5 02/19-26/91 11 +/- 1 10+/- 1 11 +/- 2 13+/- 2 12+/- 2 11 +/- 2 12+/- 2 12+/- 2 12+/- 2 MARCH 02/26-05/91 9.9 +/- 1.5 10+/- 1 13+/- 2 11 +/- 2 (a) 12+/- 2 11 +/- 1 11 +/- 2 (a) 10+/- 1 11 +/- 2 03/05-12/91 14+/- 2 17+/- 2 20+/- 2 21 +/- 2 18+/- 2 16+/- 2 19+/- 2 16+/- 2 18+/- 5 03/12-19/91 7.4+/- 1.3 7.5+/- 1.3 9.5+/- 1.3 12+/- 2(b) 7.5+/- 1.2 6.3 +/- 1.2 7.6+/- 1.3 7.3 +/- 1.3 (c) 8+/- 4 03/19-26/91 19+/- 2 22+/- 2 21 +/- 2 23+/- 2 20+/- 2 20+/- 2 21 +/- 2 21 +/- 2 21 +/- 3 03/26-02/91 15+/- 2 14+/- 2 18+/- 2 16+/- 2 14+/- 2 13+/- 2 16+/- 2 16+/- 2 15+/- 3 Qtr. Avg. 14 +/- 8 15 +/-10 17 +/-9 18 +/- 9 15 +/-9 15 +/- 9 17 +/-11 15 +/- 8 16 +/-9 +/- 2 s.d. A.e.BlL 04/02-09/91 14+/- 2 16+/- 2 18+/- 2 16+/- 2 (d) 16+/- 2 15+/- 2 15+/- 2 16+/- 3 04/09-16/91 12+/- 2 12+/- 2 14+/- 2 16+/- 2 12+/- 2 12+/- 2 12+/- 2 12+/- 2 13+/- 3 04/16-23/91 12+/- 2 14+/- 2 14+/- 2 14+/- 2 29+/- 6 (e) 13+/- 2 14+/- 2 12+/- 2 15+/-11 04/23-30/91 14+/- 2 15+/- 2 17+/- 2 19+/- 2 15+/- 2 15+/- 2 15+/- 2 16+/- 2 16+/- 3 MAY 04/30-07/91 13+/- 2 12+/- 2 14+/- 2 11 +/- 2 13+/- 4 12+/- 2 13+/- 2 15+/- 2 13+/- 3 05/07-14/91 18+/- 2 20+/- 2 20+/- 2 16+/- 2 26+/- 3 18+/- 2 20+/- 2 22+/- 2 20+/- 6 05/14-21/91 14+/- 2 14+/- 2 16+/- 2 14+/- 2 14+/- 2 15+/- 2 15+/- 2 14+/- 2 15+/- 2 05/21-28/91 8.6 +/- 1.4 14+/- 2 13+/- 2 12+/- 2 10+/- 2 12+/- 2 12+/- 2 14+/- 2 12+/- 4 .J.!JNf 05/28-05/91 17+/- 2 15+/- 2 20+/- 2 12+/- 1 16+/- 2 17+/- 2 19+/- 2 16+/- 2 17+/- 5 06/05-11/91 9.8 +/- 1.7 7.1 +/- 1.5 11 +/- 2 9.1 +/- 1.7 7.7+/- 1.5 9.8 +/- 1.6 8.1 +/- 1.5 9.2+/- 1.6 9+/- 3 06/11-18/91 16+/- 2 8.9 +/- 1.4 18+/- 2 14+/- 2 34+/- 4 (f) 13+/- 2 15+/- 2 17+/- 2 17+/-15 06/18-25/91 7.5 +/- 1.3 9.5 +/- 1.4 6.6+/- 1.3 5.8+/- 1.2 8.7 +/- 1.4 8.0 +/- 1.4 7.4+/- 1.3 8.9 +/- 1.4 8+/- 3 06/25-02/91 13+/- 2 11 +/- 2 15+/- 2 10+/- 1 13+/- 2 13+/- 2 12+/- 2 13+/- 2 13+/- 3 Qtr. Avg 13 +/- 6 13 +/-7 15 +/-7 13 +/- 7 16 +/-6 13 +/- 6 14 +/-7 14 +/- 7 14 +/-3 +/- 2 s.d. JULY 07/02-09/91 18+/- 2 25+/- 2 22+/- 2 16+/- 2 24+/- 2 17+/- 2 20+/- 2 19+/- 2 20+/- 7 07/09-16/91 18+/- 2 24+/- 2 17+/- 2 15+/- 2 19+/- 2 17+/- 2 18+/- 2 20+/- 2 19+/- 5 07/16-23/91 21 +/- 2 19+/- 2 17+/- 2 20+/- 2 35+/- 4 16+/- 2 19+/- 2 19+/- 2 21 +/-12 07/23-30/91 16+/- 2 16+/- 2 16+/- 2 15+/- 2 28+/- 3 15+/- 2 14+/- 2 15+/- 2 17+/- 9
TABLE B-2: GROSS BETA CONCENTRA110N IN AIR PAKTIWLATES Surry Nuclear Power Station, Surry County, Virginia - 1991 1.0 e--03 pCiJm3 +/- 2 Sigma January 1 to December 31, 1991 Page 2 of2
§TATIONS COLLECTION ss HIR BC ALL CP DOW FE NN Average DATE +/- 2 SI ma AUGUSI 07/30-06/91 14+/- 2 9.0 +/- 1.4 16+/- 2 13+/- 2 14+/- 2 11 +/- 1 13+/- 2 13+/- 2 13+/- 4 08/06-13/91 15+/- 2 18+/- 2 17+/- 2 15+/- 2 17+/- 2 14+/- 2 17+/- 2 16+/- 2 16+/- 3 08/13-20/91 18+/- 2 20+/- 2 16+/- 2 18+/- 2 17+/- 2 14+/- 2 17+/- 2 16+/- 2 17+/- 4 08/20-28/91 17+/- 2 22+/- 2 20+/- 2 21 +/- 2 19+/- 2 19+/- 2 24+/- 2 21 +/- 2 20+/- 4 08/28-03/91 14+/- 2 33+/- 4 16+/- 2 14+/- 2 35+/- 4 12+/- 2 9.5+/- 1.5 12+/- 2 18+/-20 SEeIEMEIEB 09/03-1 0/91 17+/- 2 19+/- 2 17+/- 2 20+/- 2 20+/- 2 17+/- 2 19+/- 2 20+/- 2 19+/- 3 09/10-17/91 18+/- 2 25+/- 2 23+/- 2 23+/- 2 21 +/- 2 19+/- 2 26+/- 2 25+/- 2 23+/- 6 09/17-24/91 14+/- 2 14+/- 2 14+/- 2 17+/- 2 14+/- 2 16+/- 2 16+/- 2 14+/- 2 15+/- 3 09/24-01/91 12+/- 2 16+/- 2 18+/- 2 17.+/- 2 12+/- 2 13+/- 2 19+/- 2 16+/- 2 15+/- 5 Qtr. Avg 16 +/- 5 20 +/-12 18 +/- 5 17 +/- 6 21 +/-15 15 +/- 5 18 +/- 9 17 +/-7 18 +/-4
+/- 2 s.d. OCTOBER 10/01-08/91 14+/- 2 16+/- 2 16+/- 2 18+/- 2 13+/- 2 13+/- 2 17+/- 2 14+/- 2 15+/- 4 10/08-15/91 20+/- 2 22+/- 2 22+/- 2 24+/- 2 19+/- 2 19+/- 2 23+/- 2 22+/- 2 21 +/- 4 10/15-22/91 19+/- 2 19+/- 2 17+/- 2 20+/- 2 16+/- 2 14+/- 2 20+/- 2 18+/- 2 18+/- 4 10/22-29/91 29+/- 2 24+/- 2 24+/- 2 26+/- 2 24+/- 2 24+/- 2 27+/- 2 21 +/- 2 25+/- 5 NQ~EMEIEB 10/29-05/91 25+/- 2 20+/- 2 24+/- 2 31 +/- 2 22+/- 2 22+/- 2 29+/- 2 19+/- 2 24+/- 8 11/05-12/91 24+/- 2 24+/- 2 24+/- 2 23+/- 2 21 +/- 2 23+/- 2 28+/- 2 22+/- 2 24+/- 4 11/12-19/91 25+/- 2 23+/- 2 25+/- 2 27+/- 2 21 +/- 2 21 +/- 2 24+/- 2 17+/- 2 23+/- 6 11/19-26/91 13+/- 2 11 +/- 1 11 +/- 2 14+/- 2 12+/- 2 11 +/- 2 16+/- 2 11 +/- 2 12+/- 4 DECEMl3EB 11 /26-03/91 14+/- 2 15+/- 2 13+/- 2 16+/- 2 13+/- 2 14+/- 2 15+/- 2 9.5+/- 1.4 14+/- 4 12/03-1 0/91 21 +/- 2 24+/- 2 20+/- 2 28+/- 2 21 +/- 2 24+/- 2 26+/- 2 20+/- 2 23+/- 6 12/10-17/91 15+/- 2 17+/- 2 16+/- 2 16+/- 2 15+/- 2 17+/- 2 21 +/- 2 15+/- 2 17+/- 4 12/17-23/91 17+/- 2 19+/- 2 19+/- 2 17+/- 2 17+/- 2 19+/- 2 19+/- 2 16+/- 2 18+/- 3 12/23-30/91 18+/- 2 15+/- 2 17+/- 2 15+/- 2 16+/- 2 17+/- 2 21 +/- 2 17+/- 2 17+/- 4 Qtr Avg. 20 +/-10 19 +/-8 19 +/-9 21 +/-11 18 +/-8 19 +/- 9 22 +/-9 17 +/-8 19 +/-3 +/- 2 s.d. Annual Avg. 16 +/- 9 17 +/-11 17 +/- 8 17 +/-10 18 +/-13 15 +/-8 18 +/-11 16 +/- 8 17 +/-10 +/- 2.s~d. (a) Volumes estimated based on start/stop times due to sampler timer malfunction. (b) Cause for low hours on sampler is unknown. (c) Timer malfunctioned. Volume calculated is based on interval since filter last changed. (d) Air sampler malfunctioned and exact volume unknown. See exceptions page. (e) Blown fuse resulting in low air volume. LLD not met. See exceptions page. (f) Blown fuse on power pole resulting in low air volume.
TABLE B-3: GAMMA EMITI'ER1 CONCENIRA110N IN QUARTERLY AIR PAKI1CULATES Surry Nuclear Power Station, Surry County, Virginia - 1991 1.0 e-03 pCiJm3 +/- 2 Sigma January 1 to December 31, 1991 Page 1 of 2 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 01 /02-04/02 04/02-07/02 07/02-10/01 10/01-12/30 + 2 s.d. STA-SS Be-7 117+/-12 122 +/-12 79.6 +/- 8.0 106+/-11 106 +/- 38 K-40 <10 <4 <5 <5 Co-60 < 0.4 < 0.3 < 0.4 < 0.2 Cs-134 < 0.4 < 0.2 < 0.3 < 0.2 Cs-137 < 0.4 < 0.3 < 0.3 < 0.2 Th-228 < 0.5 < 0.5 < 0.5 < 0.4 STA-HIR Be-7 112+/-11 94.3 +/- 9.4 108 +/- 11 104 +/- 10 105 +/- 15 K-40 <10 <10 <10 <6 Co-60 < 0.3 < 0.4 < 0.4 < 0.3 Cs-134 < 0.4 < 0.4 < 0.4 < 0.2 Cs-137 < 0.4 < 0.4 < 0.3 < 0.2 Th-228 < 0.5 < 0.7 < 0.5 < 0.4 STA-BC Be-7 130 +/- 13 96.4 +/- 9.6 102 +/- 10 103 +/- 10 108 +/- 30 K-40 <5 <4 < 10 <4 Co-60 < 0.3 < 0.3 < 0.3 < 0.2 Cs-134 < 0.3 < 0.2 < 0.4 < 0.2 Cs-137 < 0.2 < 0.2 < 0.3 < 0.2 Th-228 < 0.5 < 0.4 < 0.5 < 0.4 STA-ALL Be-7 136 +/- 14 108 +/- 11 132 +/- 13 119+/-12 124 +/- 26 K-40 <9 <6 <5 <4 Co-60 < 0.4 < 0.3 < 0.3 < 0.3 Cs-134 < 0.3 < 0.4 < 0.3 < 0.2 Cs-137 < 0.3 < 0.3 < 0.2 < 0.2 Th-228 < 0.5 < 0.6 < 0.5 < 0.5 STA-CP Be-7 119+/-12 117+/-12 111 +/- 11 95.7 +/- 9.6 111 +/- 21 K-40 <5 6.26 +/- 3.45 <20 <3 6.26 +/- 3.45 Co-60 < 0.3 < 0.5 < 0.4 < 0.2 Cs-134 < 0.2 < 0.4 < 0.4 < 0.2 Cs-137 < 0.2 < 0.5 < 0.4 < 0.2 Th-228 < 0.5 < 0.7 < 0.7 < 0.3 STA-DOW Be-7 112+/-11 110+/-11 104 +/- 10 94.7 +/- 9.5 105 +/- 16 K-40 <4 <6 <5 <4 Co-60 < 0.4 < 0.3 < 0.3 < 0.2. Cs-134 < 0.3 < 0.4 < 0.3 <0.2 Cs-137 < 0.3 < 0.4 < 0.3 < 0.2 Th-228 < 0.5 < 0.7 < 0.5 < 0.3 64
TABLE B-3: GAMMA EMJ1TER1 CONCENTRA110N IN QUAR'l11RLYAIR PAR11CCJLATES Surry Nuclear Power Station, Surry County, Virginia - 1991 1.0 e-03 pCiJm3 +/- 2 Sigma Januaiy 1 to December 31, 1991 Page 2 of2 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 01 /02-04/02 04/02-07/02 07/02-10/01 10/01-12/30 + 2 s.d. STA-FE Be-7 118+/-12 107 +/- 11 98.3 +/- 9.8 127 +/- 13 113 +/- 25 K-40 <4 <10 <4 <8 Co-60 < 0.3 < 0.4 < 0.3 < 0.3 Cs-134 < 0.2 < 0.4 < 0.2 < 0.3 Cs-137 < 0.2 < 0.4 < 0.2 < 0.3 Th-228 < 0.3 < 0.6 < 0.4 < 0.4 STA-NN Be-7 114 +/- 11 111 +/- 11 114 +/- 11 95.6 +/- 7.1 109 +/- 18 K-40 < 20 <10 <7 <6 Co-60 < 0.5 < 0.4 < 0.3 < 0.4 Cs-134 < 0.5 < 0.4 < 0.3 < 0.3 Cs-137 < 0.5 < 0.4 < 0.3 < 0.3 Th-228 < 0.7 < 0.6 < 0.7 < 0.5 1 All gamma emitters other than those listed were < LLD. 65
TABLE ~4: GAMMA EMnTERl AND TRll1UM CONCENTRA110NS IN RIVER WAffiR e Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/1 +/- 2 Sigma January 1 to December 31, 1991 Page 1 of 2 Collection Station Date Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 JANUARY-1991 CHIC 01/23 <40 < 200 < 0.2 <5 <20 <9 <9 HIP 01/23 <40 <60 < 0.2 <4 <20 <7 <7 NN 01/23 <30 <60 < 0.2 <3 <10 <6 <6 SD 01/23 < 30 <60 < 0.2 14.3 +/- 3.6 (a) < 10 <6 <6 SI 01/23 <40 <90 < 0.2 <5 <20 <7 <8 SW 01/23 <60 < 100 < 0.2 <6 <30 < 10 <10 EEBBUABY-l 991 SD 02/19 < 20 <50 < 0.1 <4 <8 <4 <5 SW 02/19 < 30 < 100 < 0.2 <4 <10 <5 <6 MABCl::l-:1991 CHIC 03/22 <30 <40 < 0.2 <3 <20 <7 <6. < 200 HIP 03/21 < 40 < 200 < 0.2 <5 <20 <10 <8 < 200 NN
- 03/21 < 30 156 +/- 36 < 0.2 <4 <20 <8 <7 < 200 SD 03/22 <30 <50 < 0.2 <4 <20 <7 <7 470 +/- 120 SI 03/21 <40 <90 < 0.2 <5 <20 <9 <8 < 200 SW 03/22 < 40 <70 < 0.2 <5 <20 <9 <10 < 200 e AeBIL-l99l SD 04/16 < 30 <60 < 0.1 <4 <10 <6 <7 SW 04/16 <40 < 100 < 0.1 <4 <20 <6 <7 MAY-l99l CHIC 05/09 <30 <40 < 0.2 <3 <20 <10 <6 < 200 HIP 05/09 < 30 < 80 < 0.1 <4 < 30 <10 <6 430 +/-110 NN 05/09 <30 <50 < 0.2 <3 <20 <10 <5 < 100 SD 05/09 < 30 <50 < 0.3 28.9 +/- 3.3 <20 <9 <5 2100 +/-200 SI 05/09 < 40 < 100 < 0.2 <4 < 30 <10 <7 280 +/-110 SW 05/09 <40 < 100 < 0.1 <4 <30 <10 <7 < 200 JUNE-1991 SD 06/18 <50 139 +/-41 < 0.2 <5 < 20 < 10 <8 SW 06/18 <40 < 100 < 0.1 <5 <20 <10 <9 JULY-1991 CHIC 07/26 < 40 < 100 < 0.2 <4 <30 <10 <7 HIP 07/25 < 30 <40 < 0.2 <3 < 20 <10 <6 NN 07/25 <30 131 +/-28 < 0.2 <3 <30 <10 <7 SD 07/26 < 30 73.5 +/-23.7 < 0.2 <3 <20 < 10 <5 SI 07/25 < 30 81.7 +/-28.5 < 0.2 <3 <20 <9 <5 SW 07/26 <40 78.1 +/-26.1 < 0.2 <4 <30 <10 <6 AUG!JSI-l99l e SD SW 08/20 08/20
<50
< 30
< 100 66.9 +/-25.8
< 0.1
< 0.1
<5
<3
<30
<20
<10
<8
<8
<5
(,6
TABLE B-4: GAMMA EMJ1TER1 AND TRn1UM CONCENTRAnONS IN RIVER WA1ER Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/1 +/- 2 Sigma January 1 to December 31, 1991 Page 2 of 2 Collection Station Date Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 SEPTEMBER-1991 CHIC 09/04 <30 25.9 +/-14.3 < 0.1 <3 <20 <8 <7 < 200 HIP 09/04 < 30 < 90 < 0.1 <4 <20 <8 <6 140 +/- 80 NN 09/04 < 30 174 +/-32 < 0.1 <3 <10 <6 <5 < 100 SD 09/04 < 30 < 90 < 0.1 <3 <20 <8 <5 < 100 SI 09/04 <30 80.9 +/-27.2 < 0.1 <3 <20 <8 <6 < 100 SW 09/04 <40 < 100 < 0.1 <4 < 20 <9 <6 < 200 QCIQBEB-1991 SD 10/15 <40 < 100 < 0.1 <5 < 20 <7 <7 SW 10/15 <40 < 100 < 0.1 <5 < 20 <7 <8
)
~Q~EMBEB-1991 CHIC 11/06 <40 291 +/-40 < 0.1 <5 < 20 <8 <7 200 +/- 100 HIP 11/05 <40 < 100 < 0.3 <5 < 20 <8 <7 460+/- 80 NN 11/05 <40 < 200 < 0.2 <5 < 30 <10 <8 < 200 SD 11/05 < 40 94.8 +/-30.0 < 0.2 <4 <20 <8 <7 < 200 SI 11/05 <50 < 200 < 0.2 <5 < 30 <9 <9 300+/- 80 SW 11/06 < 50 < 100 < 0.2 <5 < 20 <8 <8 < 100 DECEMBEB-l 991 SD 12/17 <30 < 80 < 0.5 <3 <10 <5 <5 SW 12/17 <40 < 100 < 0.2 <4 <20 <6 <6 1 All gamma emitters other than those listed were < LLD. (a) Confirmed by analysis of a second aliquot. 67
TABLE B-5: GAMMA EMJ1TER1 AND TRrI'lUM CONCENTRA11QNS IN RIVER WAWR e State-Sp"/it Samples Suny Nuclear Power Station, Surry County, Virginia - 1991 pCi/1 +/- 2 Sigma Januaiy 1 to December 31, 1991 Page 1 of 1 Collection Month Date Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 SCOTLAND WH. (SW) Jan 01/31 < 30 <50 < 0.5 <3 <20 <7 <6 Feb 02/28 <50 < 100 < 0.4 <5 <30 <10 <7 March 03/31 <30 <40 < 0.6 <3 <20 <8 <5 < 200 April 04/30 <50 < 100 <1 <4 <30 <10 <7 May 05/31 <30 <30 < 0.3 <2 <20 <10 <4 < 200 June 06/30 < 40 <50 < 0.4 <3 <30 <10 <7 July 07/31 <40 < 100 < 0.4 <4 <30 < 10 <6 August 08/31 <30 <40 < 0.3 <3 < 20 <10 <5 Sept 09/30 <40 < 100 < 0.3 <5 <20 <9 <8 < 100 Oct 10/31 <40 71.8 +/- 29.2 < 0.4 <4 <20 <10 <6 Nov 11/30 < 40 < 100 < 0.3 <5 <20 <8 <8 Dec 12/31 <40 < 60 < 0.4 <4 <20 <10 <7 810 +/- 90 Average+/- 2 s.d. 71.8 +/- 29.2 810 +/- 90 SURRY DIS, (SD) e Jan 01/31 <30 <50 < 0.5 <3 <20 <6 <6 620 +/- 50 Feb 02/28 <30 <60 < 0.4 <5 <20 <10 <6 March 03/31 < 40 347 +/- 41 < 0.8 <4 <30 <10 <6 April 04/30 <60 < 100 < 0.5 <5 < 20 <10 <8 1200 +/- 100 May 05/31 <30 <50 < 0.2 <3 <20 <9 <5 June 06/30 <30 <50 < 0.4 <3 <30 <10 <6 July 07/31 < 30 60.2 +/- 26.3 < 0.4 <3 <20 <10 <5 < 100 Aug 08/31 <30 96.6 +/- 29.5 < 0.3 <3 < 20 <9 <6 Sept 09/30 <50 < 200 < 0.3 <5 * <20 < 10 <9 Oct 10/31 <50 < 100 < 0.5 <5 <40 <10 <8 300 +/- 80 Nov 11/30 < 30 58.0 +/- 28.8 < 0.4 <4 <20 <7 <6 Dec 12/31 <40 98.0 +/- 29.3 < 0.4 <4 <20 <10 <6 Average+/- 2. s.d. 132 +/- 243 707 +/- 912 1 All gamma emitters other than those listed were < LLD. (a) Sample lost during original shipment; replacement received 4/26/91 e (B
TABLE B-6: GAMMA EMJTTERl AND TRITIUM CONCENTRA'nONS IN WELL WA.1ER e Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/1 +/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Collection Date Station Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 EIRSI QUARTEB 03/19 BC < 30 <60 < 0.2 <3 < 20 <9 <7 < 200 03/26(a) HIR < 30 <40 < 0.1 <3 <10 <6 <6 < 200 03/19 JMTN < 30 <60 < 0.2 <4 < 20 <6 <7 < 200 03/19 ss <30 <60 <0.2 <4 <20 <7 <6 < 200
~E,QlSll Ql!ABTER 06/18 BC <40 < 100 < 0.1 <4 <20 < 10 <8 < 200 06/18 HIR < 30 <50 < 0.1 <3 < 20 <8 <6 < 200 06/18 JMTN <30 <50 < 0.2 <3 < 20 <9 <6 < 200 06/18 ss <40 < 100 < 0.1 <4 < 20 <10 <7 < 200 IWBll Ql!ARTEB 09/17 BC <40 < 90 < 0.1 <4 <20 <9 <6 < 100 09/17 HIR <30 <60 < 0.1 <4 < 20 <8 <8 < 80 09/17 JMTN < 30 <50 < 0.1 <4 < 20 <9 <6 < 100 09/17 ss < 30 <50 < 0.1 <3 < 20 <9 <6 < 90 FOURTH QUARTER e 12/17 12/17 12/17 BC HIR JMTN
<30
<30
< 20
<50
< 80
<40
< 0.2
< 0.2
< 0.1
<3
<3
<3
<10
<10
<10
<6
<5
<4
<6
<5
<6 200 200 200 12/17 ss < 30 <40 < 0.2 <3 <10 <5 <6 < 200 1 All gamma emitters other than those listed were < Ll.D.
(a) Sample lost during original shipment; replacement received 4/26/91 e 6)
TABLE B-7: GAMMA EMnTERl CONCENTRA110NS IN SILT Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (dry) +/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Station CHIC HIP NN POS SD SI Coll. Date 03/22 03/22 03/21 03/21 03/22 03/21 Be-7 <500 <500 <400 <600 <400 1100+/- 430 K-40 18200+/- 1800 14000+/- 1400 15800+/- 1600 16200+/- 1600 14300 +/- 1400 15900+/- 1600 Mn-54 <40 <50 <40 <50 <50 <40 Co-58 <40 <70 <40 <60 <50 69.9+/-36.2 Co-60 170+/-43 402+/-58 71.1 +/-39.4 357+/-58 804+/-80 458+/-46 Cs-134 <60 <70 <50 115+/- 44 122+/-44 173+/-37 Cs-137 663+/-66 836+/-84 351 +/-46 835+/-83 883+/-88 1120+/- 110 Ra-226 3230+/-730 2460+/-750 1210+/-530 2570+/-810 1940+/- 690 1780+/- 650 Th-228 1500+/- 150 1440+/- 140 1090+/- 110 1260+/- 130 1170+/- 120 1280+/- 130 Icon. Date 09/04 09/04 09/04* 09/04 09/04 09/04 Avg+/- 2 s. d. I Be-7 <500 <400 <300 <500 <600 <300 1100+/-430 K-40 15100 +/- 1500 14900+/- 1500 16700+/- 1700 15500+/- 1600 14500 +/- 1500 7550+/-760 14888+/-5166 Mn-54 <40 <40 <30 <40 <60 <30 Co-58 <40 <40 <30 <50 337+/-48 <30 203+/-378 Co-60 113+/-42 <40 <50 274+/-50 1000+/-100 72.2+/-36.9 372+/-628 e Cs-134 <50 <50 <40 <50 155+/-52 <30 141 +/- 55 Cs-137 897+/-90 <40 310+/-31 582+/-62 1150 +/-110 164+/-31 708+/-652 Ra-226 2600+/-680 1970 +/- 580 1580+/- 570 2070+/-620 3160+/-840 1200+/- 370 2148+/- 1347 Th-228 1210 +/- 120 927+/-93 1130+/-110 1280+/- 130 1190+/- 120 447+/- 45 1160+/-541 TABLE B-8: GAMMA EMJ1TER1 CONCENTRA110NS IN SHOREUNE SEDIMENT Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (dry)+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Station HIR Burwell's HIR Burwell's Average Collection Date 02/26 02/26 08/28 08/28 +/- 2 s.d. Be-7 < 200 < 200 < 200 < 200 K-40 5830 +/- 580 1770 +/- 250 4520 +/- 450 1810 +/- 280 3483 +/- 4053 Co-60 < 20 < 20 < 20 <20 Cs-134 < 20 <20 < 20 < 20 Cs-137 <30 < 20 < 20 < 20 Ra-226 < 400 < 500 < 400 554 +/- 305 554 +/- 305 Th-228 < 40 <50 213 +/- 35 < 50 213 +/- 35 1 All gamma emitters other than those listed were < LLD.
'70
TABLE B-9: GAMMA EMI1TER1, STR.ONilUM-89, AND STRONTIUM-90 CONCENTRAilON INMHK Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/k:g (wet)+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 2 NUCLIDE LEE HALL EPPS CP WMS JDKS JANUARY Sr-892 <4 <5 <4 Sr-902 0.93 +/- 0.56 0.71 +/- 0.48 < 0.8 K-40 1370 +/- 140 1300 +/- 130 1380 +/- 140 1350 +/- 130 1250 +/- 130 Cs-137 <5 <4 <4 <4 <5 1-131 < 0.2 < 0.3 < 0.3 < 0.3 < 0.5 EEEIB!JABY K-40 1420 +/- 140 1270 +/- 130 1350 +/- 140 1270 +/- 130 1150 +/- 120 Cs-137 <4 <4 <4 <5 <5 1-131 < 0.2 < 0.2 < 0.1 < 0.2 < 0.2 MARCH K-40 1170 +/- 120 1250 +/- 130 1320 +/- 130 1250 +/- 120 1220 +/- 120 Cs-137 <4 <4 <4 <5 <5 1-131 < 0.1 < 0.1 < 0.1 < 0.2 < 0.2 APRIL Sr-892 <4 <3 <4 Sr-902 < 0.2 < 0.2 2.6+/- 0.4 K-40 1230 +/- 120 1320 +/- 130 1440 +/- 140 1540 +/- 150 1220 +/- 120 Cs-137 <5 <5 <4 <4 <5 1-131 < 0.2 < 0.1 < 0.1 < 0.4. < 0.1
.MAY K-40 1270 +/- 130 1390 +/- 140 1270 +/- 130 1400 +/- 140 1190 +/- 120 Cs-137 <4 <4 <5 <4 <4 1-131 < 0.2 < 0.2 < 0.1 < 0.2 < 0.2 4J.lNE K-40 1240 +/- 120 1220 +/- 120 1260 +/- 130 1170 +/- 120 1260 +/- 130 Cs-137 <4 <4 <4 <4 <4 1-131 < 0.1 < 0.2 < 0.2 < 0.2 < 0.2
.J..!J.LY Sr-892 <2 <1 <3 Sr-902 0.16 +/- 0.10 0.33 +/- 0.11 1.6 +/- 0.3 K-40 1150 +/- 120 1360 +/- 140 1590 +/- 160 1340 +/- 130 1360 +/- 140 Cs-137 <3 <3 <6 <4 <4 1-131 < 0.1 < 0.1 < 0.1 < 0.2 < 0.1 71
TABLE B-9: GAMMA EMI1TER1, STR.ONilUM-89, AND STRONTIUM-90 CONCENTRADON INMHK Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (wet)+/- 2 Sigma January 1 to December 31, 1991 Page 2 of 2 NUCLIDE A!JGUSI LEE HALL EPPS CP WMS JDKS I K-40 1220 +/- 120 1210 +/- 120 1240 +/- 120 1280 +/- 130 1250 +/- 120 Cs-137 <6 <5 <6 <4 <6 1-131 < 0.1 < 0.1 < 0.1 < 0.1 < 0.2 SEeIEMEIEB K-40 1300 +/- 130 1280 +/- 130 1290 +/- 130 1280 +/- 130 1280 +/- 130 Cs-137 <4 <4 <4 <5 <6 1-131 < 0.1 < 0.2 < 0.1 < 0.1 < 0.1 OCTOBER Sr-89 2 <1 < 0.9 <2 Sr-902 0.39 +/- 0.14 0.32 +/- 0.08 0.38 +/- 0.14 K-40 1310 +/- 130 1150 +/- 120 1190 +/- 120 1280 +/- 130 1350 +/- 130 Cs-137 <5 <4 <5 <4 <7 1-131 < 0.1 < 0.1 < 0.1 < 0.2 < 0.2 NOVEMBER K-40 1180 +/- 120 1400 +/- 140 1210 +/- 120 1370 +/- 140 1300 +/- 130 Cs-137 <6 <4 <4 <4 <5 1-131 < 0.3 < 0.3 < 0.2 < 0.3 < 0.2 DECEMEIEB K-40 1360 +/- 140 1200 +/- 120 1360 +/- 140 1380 +/- 140 1230 +/- 120 Cs-137 <4 <5 <5 <4 <4 1-131 < 0.2 < 0.2 < 0.3 < 0.3 < 0.2 1 All gamma emitters other than those listed were <LLD. 2 Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples (Epps, Lee Hall) and Colonial Parkway(CP) sample at the request of the State of Virginia. 72
TABLE ~10: GAMMA EMl'ITER1 CONCENTRA110N IN CLAMS Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (wet)+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Station Date Type Be-7* K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 CHIC 01/23/91 Clams < 200 233 +/- 136 <20 <10 <10 < 300 <30 03/22/91 Clams < 200 268 +/- 102 <20 <10 < 20 < 300 <30 05/09/91 Clams < 300 383 +/- 219 <20 < 20 <20 < 500 <40 07/26/91 Clams < 300 272 +/- 157 <30 < 20 <30 < 500 <50 09/04/91 Clams < 500 < 700 <40 <40 <50 < 700 < 80 11/06/91 Clams < 300 <400 <20 <20 < 20 < 500 < 50 ~ 01/23/91 Clams < 200 280+/- 113 < 20 < 20 <20 < 300 <30 03/22/91 Clams < 200 < 600 < 20 < 20 < 20 < 300 < 30 05/09/91 Clams < 300 < 400 <20 <30 < 20 < 400 <40 07/26/91 Clams < 300 < 400 <30 < 20 < 20 < 300 <30 09/04/91 Clams < 300 < 500 < 30 < 20 <30 < 500 <50 11/05/91 Clams < 300 457 +/- 252 <30 < 30 <40 < 500 <50 SO - (Stott S~lit Sam~l!~1) 01/23/912 Clams < 200 260 +/- 140 < 20 < 20 24.9 +/- 9.4 < 300 < 30 02/27/912 Clams < 200 227+/- 97 <20 <10 < 20 < 300 <30 04/29/912 Clams < 300 470 +/- 232 < 30 < 20 < 30 < 700 <60 07/09/912 Clams < 300 < 500 <30 < 30 <30 < 500 <60 09/16/912 Clams < 200 < 400 <20 < 20 < 20 < 400 <40 11/07/912 Clams < 200 < 500 < 20 < 20 < 20 < 400 <40 .1::1.J.e 01/23/91 Clams < 200 < 500 <20 < 20 < 20 < 300 <30 03/21/91 Clams < 100 419 +/- 89 <10 <9 <10 < 200 <20 05/09/91 Clams < 300 < 900 <30 < 30 <30 < 600 <50 07/25/91 Clams < 400 535 +/- 235 <30 < 30 <30 < 400 < 40 09/04/91 Clams < 400 < 900 <30 < 30 < 30 < 500 <40 11/05/91 Clams < 400 813 +/- 228 <30 <30 <30 < 500 <50 LC 01/23/91 Clams < 200 <500 <20 <20 < 20 < 300 <30 03/21/91 Clams < 100 443 +/- 101 < 10 < 10 <10 < 200 < 20 05/09/91 Clams < 300 <500 <30 < 30 < 30 < 700 <60 07/25/91 Clams < 300 702 +/- 172 <20 < 20 < 20 <400 < 40 09/04/91 Clams < 400 < 1000 <40 < 40 < 40 < 600 <60 11/05/91 Clams < 300 < 600 <30 < 20 <30 < 800 < 70 Average+/- 2 s.d. 412 +/- 357 24.9 +/- 9.4 1 All gamma emitters other than those listed were <LLD.
TABLE B-11: GAMMA EMJ1TER1 CONCENTRA110N IN OYSTERS Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (wet)+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Statioo DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 RLS 01/23/91 Oysters < 200 387 +/- 124 <20 <20 <20 <300 < 30 03/21/91 . Oysters < 100 384+/- 92 <9 <10 <10 < 200 < 20 05/09/91 Oysters < 300 312 +/- 184 < 30 < 30 <30 < 400 <40 07/25/91 Oysters < 400 627 +/- 193 <30 <30 <20 < 500 <50 09/04/91 Oysters < 400 1350 +/- 360 <40 <30 <30 < 600 < 60 11/05/91 Oysters < 300 494 +/- 218 <30 <30 <30 < 500 < 50 .D..W.S. 01/23/91 Oysters < 300 < 500 <20 < 20 <20 < 300 < 30 03/21/91 Oysters < 100 464 +/- 103 <10 <10 <10 < 200 <20 05/09/91 Oysters < 200 638 +/- 234 <30 <20 <20 < 400 <40 07/25/91 Oysters 263 <30 <20 <20 < 600 <50 09/04/91 Oysters < 300 666 +/- 333 < 30 < 30 < 30 < 600 < 50 11/05/91 Oysters < 300 891 +/- 271 <30 < 20 <30 < 500 < 40 fQS 01/23/912 Oysters < 200 452 +/- 134 < 20 <20 < 20 < 300 <30 01/23/91 Oysters < 200 534 +/- 127 <10 < 10 <10 < 200 < 20 02/27/912 Oysters < 100 342 +/- 127 <10 <10 < 10 < 300 < 20 03/21/91 Oysters < 100 190 +/- 100 <10 <10 <20 < 300 < 20 04/30/912 Oysters < 200 525 +/- 248 < 20 < 20 < 20 < 400 <40 05/09/91 Oysters < 300 563 +/- 220 <30 < 30 < 20 < 400 < 40 07/10/912 Oysters < 300 455 +/- 232 <30 <20 <20 < 500 < 50 07/25/91 Oysters < 400 671 +/- 241 <30 <30 < 20 < 500 <40 09/04/91 Oysters < 400 534 +/- 291 < 30 < 30 <40 < 800 < 80 09/13/912 Oysters < 300 560 +/- 282 <30 < 20 <20 < 500 < 50 11/05/91 Oysters < 200 840 +/- 249 <30 <20 <30 < 400 <40 11/07/912 Oysters < 300 600 +/- 265 <30 <20 <20 < 600 <50 Average +/- 2 s.d. 565 +/- 466 1 All gamma emitters other than those listed were <LLD. 2 State split samples. 74
TABLE B-12: GAMMA EMl1TER1 CONCENTRA710N IN CRABS Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (wet)+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Station Date Type Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 .s.D. 06/13/91 Crabs < 100 1390 +/- 140 <10 <10 <10 < 200 < 20 TABLE B-13: GAMMA EMITJ'ERI CONCENTRA710N IN FISH Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (wet)+/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 04/25/91 SD
- Catfish 1870 +/- 190 <10 <10 <20 05/10/91 SD White Perch 2010 +/- 580 < 40 <60 <50 10/03/91 SD Catfish 1840 +/- 240 < 30 <30 < 30 10/28/91 SD White Perch 2150 +/- 320 <40 <40 <40 Average +/- 2 s.d. 1968 +/- 285 TABLE B-14: GAMMA EMITJ'ERI CONCENTRA710N IN VEGETA710N Surry Nuclear Power Station, Surry County, Virginia - 1991 pCi/kg (wet) +/- 2 Sigma January 1 to December 31, 1991 Page 1 of 1 Sample Collection Station Type Date Be-7 K-40 1-131 Cs-134 Cs-137 Ryan's Garden2 Kale 04/16 < 100 5240 +/- 520 <30 < 20 < 20 Poole's Garden2 Kale 05/28 < 100 7440 +/- 740 < 30 <10 <20 Carter's Garden2 Cabbage 07/02
- 107 +/- 52 2150 +/- 220 <20 <6 10.0 +/- 4.6 Brock's Garden2 Peanuts 10/08 < 100 5410 +/- 540 <50 <10 < 20 Slade's Garden Peanuts 10/02 < 100 5290 +/- 530 <60 <10 <10 Brock's Garden Corn 10/08 <60 3860 +/- 390 <20 <7 <7 Luca's Garden2 . Kale 10/22 < 100 3760 +/- 380 < 30 <20 < 20 Slade's Garden2 Corn 10/24 <50 3160 +/- 320 <30 <5 <6 Slade's Garden2 Soybeans 12/03 < 100 15200 +/- 1500 <30 < 20 < 20 Brock's Garden Soybeans 12/03 < 100 15300 +/- 1500 <30 <20 < 20 Average+/- 2 s.d. 107 +/- 52 6681 +/- 9486 10.0 +/- 4.6 1 All gamma emitters other than those listed were <llD.
2 State split samples. 75
TABLE JJ.15: DIRECT RADIA110N MEASUREMENTS - QUARTERLY 11D RESUL1S e Surry Nuclear Power Station, Surry County, Virginia - 1991 mR/month +/- 2 Sigma - Set 1 - *09s January 1 to December 31, 1991 Page 1 of 1 Station First Second Third Fourth Average Number Quarter Quarter Quarter Quarter + 2 s.d. 02 7.2 +/- 0.2 8.0+/-0.5 7.2 +/- 0.9 7.1 +/- 0.7 7.4+/- 0.8 03 7.6 +/- 0.4 8.5+/-0.9 7.0+/- 0.5 7.5 +/- 0.6 7.7 +/- 1.2 04 5.9 +/- 0.3 6.5 +/- 1.0 6.0+/- 0.5 5.1 +/- 0.4 5.9 +/- 1.2 05 5.5 +/- 0.4 6.9 +/- 0.1 5.6+/- 0.6 4.7+/- 0.2 5.7+/- 1.8 06 6.1 +/- 0.4 7.8 +/- 0.4 6.0 +/- 0.7 7.5 +/- 1.2 6.9 +/- 1.9 07 5.6+/- 0.2 6.6+/- 0.5 5.5 +/- 0.1 6.6 +/- 1.1 6.1 +/- 1.2 08 5.6+/- 0.3 7.2 +/- 0.4 5.7 +/- 0.4 6.1 +/- 0.4 6.2 +/- 1.5 09 5.7 +/- 0.4 7.0+/- 0.5 5.4+/- 0.5 6.2 +/- 0.6 6.1 +/- 1.4 10 5.5 +/- 0.3 6.6+/- 0.4 5.5 +/- 0.6 6.1 +/- 0.4 5.9 +/- 1.1 11 5.7 +/- 0.3 6.8+/- 0.3 5.5 +/- 0.4 6.4 +/- 1.0 6.1 +/- 1.2 12 6.1 +/- 0.8 6.8+/- 0.4 5.6+/- 0.3 6.7+/-1.0 6.3 +/- 1.1 13 6.3+/- 0.6 6.9 +/- 1.1 6.1 +/- 0.2 6.6 +/- 0.2 6.5 +/- 0.7 14 6.4+/- 0.5 7.5 +/- 0.5 6.4 +/- 0.4 6.8 +/- 0.5 6.8 +/- 1.0 15 5.5 +/- 0.2 6.3+/- 0.3 5.3+/- 0.9 5.9 +/- 0.6 5.8+/- 0.9 16 5.8 +/- 0.5 6.3+/- 0.4 5.2 +/- 0.3 6.4+/- 0.7 5.9+/-1.1 17 5.3 +/- 0.2 6.4+/- 0.4 5.0+/- 0.8 5.6 +/- 0.4 5.6 +/- 1.2 18 4.3+/- 0.2 5.5 +/- 0.3 4.6+/- 0.4 4.7+/- 0.3 4.8 +/- 1.0 19 5.0 +/- 0.1 5.9 +/- 0.1 5.1 +/- 0.7 5.7 +/- 0.5 5.4 +/- 0.9 20 4.6+/- 0.2 6.1 +/- 1.4 4.5 +/- 0.2 5.1 +/- 0.4 5.1 +/- 1.5 21 5.3 +/- 0.1 5.9 +/- 0.2 5.0+/- 0.5 5.5 +/- 0.7 5.4+/- 0.8 22 4.9 +/- 0.2 5.5 +/- 0.2 4.6 +/- 0.5 5.6 +/- 0.1 5.2 +/- 1.0 23 5.8 +/- 0.1 6.7+/- 0.8 5.5 +/- 0.3 6.4 +/- 0.6 6.1 +/- 1.1 24 5.5 +/- 0.3 6.1 +/- 0.4 5.2 +/- 0.2 5.7 +/- 0.3 5.6+/- 0.8 25 5.5 +/- 0.2 6.4+/- 0.6 5.3+/- 0.3 6.3 +/- 0.4 5.9 +/- 1.1 26 5.0+/- 0.3 6.2 +/- 0.3 4.8+/- 0.5 5.4+/- 0.4 5.4 +/- 1.2 27 4.6 +/- 0.2 6.3+/- 0.5 4.6+/- 0.9 5.1 +/- 0.3 5.2 +/- 1.6 28 5.6+/- 0.3 6.6 +/- 0.3 5.4 +/- 0.8 5.8 +/- 0.3 5.9 +/- 1.1 29 4.7 +/- 0.2 5.8+/- 0.3 4.4+/- 0.3 4.7 +/- 0.5 4.9 +/- 1.2 30 5.0 +/- 0.1 (a) 5.1 +/- 0.4 5.2 +/- 0.2 5.1 +/- 0.2 31 4.7 +/- 0.3 5.8+/- 0.5 4.1 +/- 0.3 4.7 +/- 0.1 4.8+/- 1.4 32 5.0 +/- 0.2 6.6+/- 0.5 4.6 +/- 0.2 5.3+/- 0.3 5.4 +/- 1.7 33 5.7+/- 0.3 6.4 +/- 0.5 5.2 +/- 0.2 6.4 +/- 0.9 5.9 +/- 1.2 34 5.7 +/- 0.3 6.8 +/- 0.4 5.4+/- 0.5 6.3 +/- 0.7 6.1 +/- 1.2 35 5.8+/- 0.3 6.9 +/- 0.4 5.7 +/- 0.3 6.4 +/- 0.5 6.2 +/- 1.1 36 6.6+/- 0.6 7.3+/- 0.4 6.3+/- 0.5 6.7+/- 0.5 6.7+/- 0.8 37 5.5 +/- 0.2 6.8+/- 0.2 5.0+/- 0.2 5.9 +/- 0.5 5.8 +/- 1.5 38 7.3 +/- 0.4 8.3 +/- 0.8 6.7 +/- 0.4 7.7 +/- 0.7 7.5 +/- 1.3 39 5.3+/- 0.3 6.4+/- 0.5 5.1 +/- 0.5 5.8 +/- 0.2 5.7 +/- 1.2 40 4.3 +/- 0.1 5.6 +/- 1.1 3.9 +/- 0.1 4.0 +/- 0.3 4.5 +/- 1.6 41 5.8 +/- 0.3 7.4 +/- 0.9 5.6 +/- 0.2 6.7 +/- 0.1 6.4+/- 1.7 42 5.4+/- 0.4 5.4 +/- 0.1 5.0 +/- 0.4 5.9 +/- 0.3 5.4 +/- 0.7 43 5.1 +/- 0.2 5.0+/- 0.4 5.0+/- 0.9 6.0 +/- 0.4 5.3 +/- 1.0 Average 5.6 +/- 1.5 6.6 +/- 1.5 5.4 +/- 1.4 5.3 +/- 1.4 5.7 +/- 1.2
+/- 2 s.d.
(a) no missing.
TABLE B-16: DIRECI' RADIA110N MEASUREMENTS-QUAKIERLY 1W RESULTS Surry Nuclear Power Station, Surry County, Virginia - 1991 mR/month +/- 2 Sigma - Set 2 - 099 January 1 to December 31, 1991 Page 1 of 1 Station First Second Third Fourth Average Number Quarter Quarter Quarter Quarter +/- 2 s.d. 02 7.0+/- 0.4 7.7+/-1.0 6.6+/- 0.5 7.0+/- 0.3 7.1 +/- 0.9 03 6.9 +/- 0.4 8.4+/- 0.5 6.7 +/- 0.3 6.1 +/- 0.3 7.0+/- 2.0 04 5.7 +/- 0.3 7.2 +/- 0.4 5.6+/- 0.3 4.7 +/- 0.6 5.8 +/- 2.1 05 5.6+/- 0.3 7.5 +/- 1.0 5.1 +/- 0.3 6.3 +/- 1.1 6.1 +/- 2.1 06 5.9+/- 0.3 7.8 +/- 0.5 5.6 +/- 0.4 6.4 +/- 1.1 6.4 +/- 1.9 07 5.4+/- 0.2 7.3+/- 0.2 5.2 +/- 0.5 6.0+/- 0.6 6.0 +/- 1.9 08 5.5 +/- 0.4 7.4+/- 0.5 5.3+/- 0.3 5.8 +/- 0.3 6.0 +/- 1.9 09 5.4 +/- 0.3 7.2 +/- 0.7 5.1 +/- 0.3 6.1 +/- 0.3 6.0+/- 1.9 10 5.2 +/- 0.2 7.2 +/- 0.3 5.0+/- 0.3 5.7 +/- 0.4 5.8 +/- 2.0 11 5.4+/- 0.3 7.2 +/- 0.4 5.1 +/- 0.4 6.2 +/- 0.5 6.0 +/- 1.9 12 5.5 +/- 0.4 7.7 +/- 0.4 5.5 +/- 0.7 6.5 +/- 0.7 6.3 +/- 2.1 13 5.6+/- 0.3 7.1 +/- 0.2 5.3+/- 0.4 6.3 +/- 0.5 6.1 +/- 1.6 14 5.9 +/- 0.3 7.8 +/- 0.6 5.6 +/- 0.4 6.8+/- 0.8 6.5 +/- 2.0 15 5.1 +/- 0.2 7.4 +/- 0.6 4.8 +/- 0.4 6.3+/- 0.7 5.9 +/- 2.4 16 5.4+/- 0.6 6.8+/- 0.2 4.9 +/- 0.4 6.5 +/- 0.3 5.9 +/- 1.8 17 5.2 +/- 0.1 6.4 +/- 0.4 4.8+/- 0.4 5.6 +/- 0.3 5.5 +/- 1.4 18 4.2 +/- 0.2 5.9 +/- 0.8 3.8 +/- 0.1 4.5 +/- 0.3 4.6+/- 1.8 19 4.8 +/- 0.2 6.3+/- 0.6 4.5+/- 0.4 5.5 +/- 0.6 5.3+/- 1.6 20 4.7+/- 0.3 5.7 +/- 0.5 4.1 +/- 0.3 5.4 +/- 0.3 5.0 +/- 1.4 21 5.1 +/- 0.2 6.6+/-0.2 4.7+/- 0.3 5.8 +/- 0.4 5.6 +/- 1.7 22 4.5 +/- 0.2 6.0+/- 0.3 4.2 +/- 0.4 5.5 +/- 0.6 5.1+/-1.7 23 5.6+/- 0.2 (a) 5.2 +/- 0.4 6.5 +/- 0.4 5.8 +/- 1.3 24 5.2 +/- 0.2 5.8 +/- 0.2 4.9 +/- 0.8 5.8+/- 0.5 5.4+/- 0.9 25 5.1 +/- 0.4 6.3+/- 0.6 5.1 +/- 0.6 6.1 +/- 0.6 5.7 +/- 1.3 26 4.9 +/- 0.1 5.9 +/- 0.9 4.9 +/- 0.3 5.7 +/- 0.2 5.4 +/- 1.1 27 4.6+/- 0.4 5.9 +/- 0.2 4.2 +/- 0.3 5.2 +/- 0.4 5.0 +/- 1.5 28 5.3 +/- 0.1 (a) 5.1 +/- 0.3 5.9 +/- 0.9 5.4 +/- 0.8 29 4.5 +/- 0.2 5.8 +/- 0.5 4.4+/- 0.4 5.2 +/- 1.2 5.0 +/- 1.3 30 4.8+/- 0.2 5.8+/- 0.6 4.5 +/- 0.3 5.8+/- 0.7 5.2 +/- 1.4 31 4.3 +/- 0.2 5.4 +/- 0.2 4.2 +/- 0.2 5.0+/- 0.5 4.7 +/- 1.1 32 5.1 +/- 0.3 6.3+/-0.5 4.8 +/- 0.3 5.4 +/- 1.1 5.4 +/- 1.3 33 5.5 +/- 0.2 6.5 +/- 0.8 5.2+/- 0.3 5.7+/- 0.4 5.7+/-1.1 34 5.5 +/- 0.2 6.5 +/- 0.4 5.4 +/- 0.3 6.1 +/- 0.3 5.9 +/- 1.0 35 5.9 +/- 0.2 6.9 +/- 1.1 5.9 +/- 0.3 6.5 +/- 0.6 6.3+/- 1.0 36 6.3+/- 0.3 7.2 +/- 0.6 6.5 +/- 0.7 6.7+/- 0.3 6.7 +/- 0.8 37 5.1 +/- 0.2 6.4 +/- 0.4 5.7+/- 0.2 6.3 +/- 0.4 5.9 +/- 1.2 38 7.1 +/- 0.4 8.1 +/-0.7 7.5 +/- 0.5 7.5 +/- 0.3 7.6 +/- 0.8 39 5.3 +/- 0.5 6.1 +/- 0.4 5.2 +/- 0.2 6.0+/- 0.3 5.7 +/- 0.9 40 4.0+/- 0.2 5.3 +/- 0.2 4.1 +/- 0.4 4.5 +/- 0.3 4.5 +/- 1.2 41 5.6+/- 0.3 6.9 +/- 0.2 5.6 +/- 0.5 7.0 +/- 1.9 6.3+/- 1.6 42 5.1 +/- 0.2 5.0 +/- 0.4 5.1 +/- 0.4 5.7 +/- 0.6 5.2+/- 0.6 43 4.9 +/- 0.1 4.9 +/- 0.2 5.3+/- 0.8 5.4+/-0.2 5.1 +/- 0.5 Average 5.3 +/- 1.3 6.6 +/- 1.7 5.2 +/- 1.5 5.9 +/- 1.3 5.8 +/- 1.3
+/- 2 s.d.
(a) 11.D missing 77
LAND USE CENSUSI - Sector Direction Surry Nuclear Power Station, Surry County, Virginia January 1 to December 31, 1991 Nearest Resident Nearest Garden2 Nearest Cow Page 1 of 1 Nearest Goat A N 4.12 @ 008° * *
- 8 NNE 1.90@ 034° 1.90@ 034° *
- C NE 4.90@ 035° 4.91 @ 056° * **
D ENE 4.73@ 063° 4.91 @ 056° *
- E E * * *
- F ESE * * *
- G SE * * *
- H SSE 4.75@ 152° * *
- J s 1.69@ 182° 1.90@ 189° *
- K SSW 1.87@ 193° 1.87@ 193° 4.84@ 201°
- L SW 2.28@ 222° 3.65@ 224° *
- M WSW 2.82@ 243° 3.57@ 246° *
- N w 3.15 @ 260° 4.14@ 269° *
- p WNW 4.79@ 281° * *
- a NW 4.84@ 319° * *
- R NNW 3.73@ 339° 4.89@ 340° 3.65@ 337° *
- NONE 1 Locations shown by statute miles and degree heading relative to true north from radius center.
2 Area greater than 50 m2, containing broad leaf vegetation. Land Use Omsus lJata Shown on Maps, Section .l Pages 29-33 78
I- - -- - - - ANALYI1CAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed on samples collected for the Surry Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Isotopes and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979. ANALYSIS TITI.E PAGE Gross Beta Analysis of Samples ............................................................................................... 80 Airborne Particulates .................................................................................................... 81 Analysis of Samples for Tritium...............................................................................................82 Water ............................................................................................................................... 82 Analysis of Samples for Strontium-89 and -90 ....................................................................... 83 Total Water ..................................................................................................................... 83 Milk ..................................................................................................................................83 Soil and Sediment .......................................................................................................... 83 Organic Solids ................................................................................................................. 84 Air Particulates ............................................................................................................... 84 Analysis of Samples for Iodine-131 ......................................................................................... 86 Milk or Water ................................................................................................................. 86 Gamma Spectrometry of Samples .......................................................................................... 87 Milk and Water ............................................................................................................... 87 Dried Solids other than Soils and Sediment.. ............................................................. 87 Fish................................................................................................................................... 87 Soils and Sediments ....................................................................................................... 87 Charcoal Cartridges (Air Iodine) .................................................................................. 87 Airborne Particulates .................................................................................................... 88 Environmental Dosimetry ........................................................................................................89
DETERMINATION OF GROSS BETA ACIIVI7Y IN WATER SAMPLES Introduction The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved. One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size. After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchette which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps. Residue mass is determined by weighing the planchette before and after mounting the sample. The planchette is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass. Detection capability Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time. The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries . per liter for gross beta at the 4.66 sigma level (1.0 pCi/1 at the 2.83 sigma level), assuming 1 that 1 liter of sample is used and that 2 gram of sample residue is mounted on the planchette. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38.
GROSS BETA ANALYSIS OF SAMPLES Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by the customer, is counted as the blank. Calculations of the results, the two sigma error and the lower limit of detection (LLD): RESULT {pCifm3) = {{Sff) - {B/t))/(2.22 V E) TWO SIGMA ERROR {pCifm3) = 2{{Srr2) + {Bft2)) 1/2/(2.22 V E) LLD {pCi/m3) = 4.66 (81/2)/(2.22 V E t) where: s = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Num~er of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 81
ANALYSIS OF SAMPLES FOR TRITIUM Water Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 409* C. The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure. The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays. Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/1: RESULT = 2(3.234) TN VN(CG - 8)/(CN VJ TWO SIGMA ERROR = 2(3.234) TN VN(E)112/(CN VJ LLD = 3.3 (3.234)TN VN(E)112/(CN VJ where: = tritium units of the standard 3.234 = conversion factor changing tritium units to pCVI volume of the standard used to calibrate the efficiency of the detector in psia Vs = volume of the sample loaded into the detector in psia CN = the net cpm of the standard of volume VN CG = the gross cpm of the sample of volume Vs B = the background of the detector in cpm L1t = counting time for the sample E = SfT2 + Btt2 82
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(N0~ 2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN03 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Soll and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N0~2 using fuming (90& nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating 83
Srco3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Organic Solids A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N0 3) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette-and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating Srco 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N0 3) 2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating Srco 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 mg/cm2 aluminum absorber for low level beta counting. Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass: RESULT Sr-89 = (N/Dt-Bc-BA)/(2.22 VYs DFsR-89 EsR-89) TWO SIGMA ERROR Sr-89 = 2((N/Dt+Bc+BA)/.1.t) 112/(2.22 V Ys DFsR-89 EsR-89) LLD Sr-89 = 4.66((Bc+BA)/.1.t) 1/2/(2.22 V YS DFsR-89 EsR-89)
RESULT Sr-90 = (N/~t - 8)/(2.22 VY 1 Y2 DF IF E) TWO SIGMA ERROR Sr-90 = 2((N/~t+B)/~t) 1/2/(2.22 VY 1 Y2 DF E IF)) LLD Sr-90 = 4.66(B/~t)112/(2.22 VY1 Y2 IF DF E) WHERE: N = total counts from sample (counts) At = counting time for sample (min) Be = background rate of counter (cpm) using absorber configuration 2.22 = dpm/pCi V = volume or weight of sample analyzed BA = background addition from Sr-90 and ingrowth of Y-90 BA = 0.016 (K) + (K) EV/abs) (IGy_go) Ys = chemical yield of strontium DF SR-89 = decay factor from the mid collection date to the counting date for SR-89 EsR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq. aluminum absorber K = (NAt- Bc)v-gcf(Ey_go IFy.90 DFy_90Y1) DFy.90) = the decay factor for Y-90 from the "milk time to the mid 0 count time Ey.90 = efficiency of the counter for Y-90 IFy.90 = ingrowth factor for Y-90 from scavenge time to milking time IGy.90 = the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 0.016 = the efficiency of measuring SR-90 through a No. 6 absorber EV/abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm) Y1 = chemical yield of yttrium Y2 = chemical yield of strontium DF = decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency of the counter for Y-90 IF = ingrowth factor for Y-90 from scavenge time to the radio-chemical milking time 85
ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode. Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/1: RESULT = (N/At-8)/(2.22 E VY DF) TWO SIGMA ERROR = 2((N/At+B)/At) 1/2/(2.22 EVY DF) LLD = =4.66(8/At) 1/2/(2.22 EVY DF) where: N = total counts from sample (counts) At = counting time for sample (min) 8 = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efficiency of the counter for 1-131, corrected for self absorption effects by the formula E = Es( exp-0.0061 M)/( exp-0.0061 Ms) Es = efficiency of the counter determined from an 1-131 standard mount Ms = mass of Pd1 2 on the standard mount, mg M = mass of PD1 2 on the sample mount, mg 86
GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector_ coupled to a mini-computer-based data acquisition system which performs pulse height analysis .
. Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature, less than 100°C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Hsh As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Soils and Sediments Soils and sediments are dried at a low temperature, less than 100°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and analysis. Charcoal_ c.artrldges (Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector. 87
Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume of pCi/mass: RESULT = (S-8)/(2.22 t E V F DF) TWO SIGMA ERROR = 2(S+B) 1/2/(2.22 t E V F DF) LLD = 4.66(8) 1/2/(2.22 t E V F OF) where:* s = Area, in counts, of sample peak and background (region of spectrum of interest) 8 = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dprn/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams) F = fractional gamma abundance (specific for each emitted gamma) DF = decay factor from the mid-collection date to the counting date 88
ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaS04:Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner. Calculations of results and the two sigma error in net milliRoentgen (mR): RESULT = 0 =(0 1+02+03+04)/4 TWO SIGMA ERROR = 2((0 1-o)2+(02-0)2+(03-o)2+(04 -o)2)/3) 1/2 WHERE: 01 = the net mR of area 1 of the TLO, and similarly for 02, 03, and 04 01 = 11 ~R 1 -A 11 = the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source R1 = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs 0 = the average net mR of all 4 areas of the TLO.
EPA Interlaboratory Comparison Program Teledyne Isotopes participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section trending graphs (since 1981) and the 1991 data summary tables are presented for isotopes in the various sample media applicable to the Surry Power Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence. 90
- e VEPCO - SURRY POWER STATION US EPA INTERI.ABORATORY COMPARISON PROGRAM 1991 (Page 1 of 3)
EPA Date Tl Malled Date EPA EPA Tl Nonn Dev. **Warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) ***Action 01/11/91 03/07/91 04/15/91 Water Sr-89 5.0 +/- 5.0 5.00 +/- 0.00 0.00 Sr-90 5.0 +/- 5.0 5.00+/- 0.00 0.00 01/25/91 02/21/91 03/18/91 Water Gross Alpha 5.0+/- 5.0 9.00 +/- 1.00 1.39 Gross Beta 5.0+/- 5.0 7.00 +/- 0.00 0.69 02/08/91 03/22/91 04/19/91 Water Co-60 40.0+/- 5.0 39.33 +/- 3.06 -0.23 Zn-65 149.0 +/- 15.0 147.00 +/- 1.00 -0.23 Ru-106 186.0 +/- 19.0 176.67 +/- 17.56 -0.85 Cs-134 8.0 +/- 5.0 . 7.33 +/- 0.58 -0.23 . Cs-137 8.0 +/- 5.0 7.67 +/- 3.21 -0.12 Ba-133 75.0 +/- 8.0 75.67 +/- 5.51 0.14 02/15/91 03/18/91 05/03/91 Water 1-131 75.0 +/- 8.0 80.00 +/- 5.29 1.08 02/22/91 03/22/91 04/15/91 Water H-3 4418.0 +/- 442.0 4500 +/- 173.21 0.32 03/08/91 05/06/91 05/31/91 Water Ra-226 31.8 +/- 4.8 28.33 +/- 4.73 -1.25 Ra-228 21.1 +/- 5.3 16.67 +/- 2.08 -1.45 03/29/91 06/06/91 07/02/91 Air Filter Gross Alpha 25.0+/- 6.0 42.67 +/- 0.58 5.10 ***(c) Gross Beta 124.0 +/- 6.0 126.67 +/- 5.77 0.77 Sr-90 40.0 +/- 5.0 37.00 +/- 1.00 -1.04 Cs-137 40.0 +/- 5.0 43.00 +/- 5.29 1.04 04/16/91 07/25/91 Water Gross Alpha 54.0+/- 14.0 59.67 +/- 4.04 0.70 Gross Beta 115.0 +/- 17.0 110.00 +/- 0.00 -0.51 Sr-89 28.0+/- 5.0 31.00 +/- 1.00 1.04 Sr-90 26.0+/- 5.0 21.00 +/- 0.00 -1.73 Cs-134 24.0 +/- 5.0 25.00 +/- 1.00 0.35 Cs-137 25.0 +/- 5.0 24.00 +/- 1.73 -0.35 04/26/91 06/28/91 07/31/91 Milk Sr-89 32.0 +/- 5.0 24.00 +/- 3.00 -2.77 ** (d) Sr-90 32.0+/- 5.0 26.33 +/- 2.08 -1.96 1-131 60.0 +/- 6.0 53.33 +/- 2.31 -1.92 Cs-137 49.0 +/- 5.0 52.67 +/- 1.53 1.27 K 1650.0 +/- 83.0 1590.00 +/- 81.85 -1.25 91
e VEPCO - SURRY POWER STATION US EPA INTERLABORATORY COMPARISON PROGRAM 1991 (Page 2 of 3) EPA Date Tl Malled Date EPA EPA Tl Nonn Dev. **Warning Preparation Reaulta laaued Result* Media Nuclide Reaults(a) Results(b) (Known) ***Action 05/10/911 05/06/91 05/10/91 Water Sr-89 39.0 +/- 5.0 38.67 +/- 4.51 -0.12 Sr-90 24.0 +/- 5.0 22.00 +/- 1.73 -0.69 05/17/91 06/13/91 07/08/91 Water Gross Alpha 24.0 +/- 6.0 24.33 +/- 2.52 0.10 Gross Beta 46.0+/- 5.0 50.33 +/- 1.53 1.50 06/07/91 07/18/91 08/12/91 Water Co-60 10.0 +/- 5.0 10.33 +/- 0.58 0.12 Zn-65 108.0 +/- 11.0 106.00 +/- 2.65 -0.31 Ru-106 149.0 +/- 15.0 136.67 +/- 3.79 -1.42 Cs-134 15.0 +/- 5.0 13.67 +/- 1.53 -0.46 Cs-137 14.0 +/- 5.0 13.67 +/- 1.53 -0.12 Ba-133 62.0+/- 6.0 56.33 +/- 1.53 -1.64 06/21/91 07/18/91 08/12/91 Water H-3 12480 +/- 1248.0 12833.33 +/- 115.50 0.49 07/12/91 10/08/91 09/06/91 Water Ra-226 15.9 +/- 2.4 15.0 +/- 1.00 -0.65 Ra-228 16.7 +/- 4.2 14.33 +/- 2.31 -0.98 08/09/91 10/08/91 09/04/91 Water 1-131 20.0+/- 6.0 19.33 +/- 0.58 -0.19 08/30/91 10/25/91 12/04/91 Air Filter Gr-Alpha 25.0+/- 6.0 27.00 +/- 2.00 0.58 Gr-Beta 92.0+/- 10.0 100.00 +/- 0.00 1.39 Sr-90 30.0+/- 5.0 27.67 +/- 2.89 -0.81 Cs-137 30.0 +/- 5.0 33.33 +/- 3.21 1.15 09/13/91 10/25/91 12/12/91 Water Sr-89 49.0+/- 5.0 50.67 +/- 2.89 0.58 Sr-90 25.0+/- 5.0 26.00 +/- 1.00 0.35 09/20/91 10/17/91 11/04/91 Water Gr-Alpha 10.0 +/- 5.0 11.67 +/- 0.58 0.58 Gr-Beta 20.0+/- 5.0 21.00 +/- 0.00 0.35 09/27 /91 12/06/91 12/23/91 Milk Sr-89 25.0 +/- 5.0 21.00 +/- 2.65 -1.39 Sr-90 25.0+/- 5.0 19.00 +/- 0.00 -2.08 **(d) 1-131 108.0 +/- 11.0 113.33 +/- 5.77 0.84 Cs-137 30.0+/- 5.0 29.00 +/- 3.61 -0.35 K 1740.0 +/- 87.0 1503.33 +/- 75.06 -4.71 ***(e) 92
VEPCO - SURRY POWER STATION US EPA INTERLABORATORY COMPARISON PROGRAM 1991 (Page 3 of 3) EPA Date Tl Malled Date EPA EPA Tl Nonn Dev. **Warning Preparation Reaulta lasued Result* Media Nuclide Reaulta(a) Rasults(b) (Known) ***Action 10/04/91 11/15/91 12/12/91 Water Co-60 29.0 +/- 5.0 30.33 +/- 2.08 0.46 Zn-65 73.0 +/- 7.0 72.67 +/- 7.09 -0.08 Ru-106 199.0 +/- 20.0 197.67 +/- 7.51 -0.12 Cs-134 10.0 +/- 5.0 10.33 +/- 0.58 0.12 Cs-137 10.0 +/- 5.0 11.33 +/- 0.58 0.46 Ba-133 98.0 +/- 10.0 97.00 +/- 8.72 -0.17 10/18/91 11/15/91 12/04/91 Water H-3 2454.0 +/- 353.0 2333.33 +/- 57.74 -0.59 10/22/91 01/02/92 01/21/92 Water Gross Alpha 82.0+/- 21.0 55.00 +/- 4.36 -2.23 ***(f) Ra-226 22.0+/- 3.3 21.00 +/- 2.65 -0.52 Ra-228 22.2 +/- 5.6 18.00 +/- 1.00 -1.30 Gross Beta 65.0 +/- 10.0 56.00 +/- 1.00 -1.56 Sr-89 10.0 +/- 5.0 10.67 +/- 2.08 0.23 Sr-90 10.0 +/- 5.0 9.33 +/- 0.58 -0.23 Co-60 20.0 +/- 5.0 19.67 +/- 0.58 -0.12 Cs-134 10.0 +/- 5.0 10.33 +/- 2.08 0.12 Cs-137 11.0 +/- 5.0 13.67 +/- 0.58 0.92 11/08/91 01/02/92 01/21/92 Water Ra-226 6.5 +/- 1.0 5.37 +/- 0.32 -1.96 Ra-228 8.1 +/- 2.0 7.90 +/- 1.20 -0.17 (a) Average +/- experimental sigma. (b) Expected laboratory precision (1 sigma, 1 determination). (c) The sample presents a different counting geometry. The EPA deposits activity in a 3/4 inch diameter circle, on a plastic disk approximately 3/32 inch thick. A special calibration for EPA filters will be performed. The laboratory has obtained blank filters from the Las Vegas facility, and will simulate their deposits. (d) The cause for the deviation is believed to be erroneously high strontium yields, probably caused by incomplete separation of calcium. The laboratory has investigated carrier concentrations and pipeting techniques, and have found them to be correct. Further aspects of analysts' techniques are being tested. The laboratory has received a new strontium extraction material developed at Argonne National Laboratory. Experiments with this method to achieve better separation of calcium were completed and procedure PR0-032-105 was implemented on 2/1/92. (e) There is no apparent cause for the low K-40 results. Two other isotopes spiked in the.sample were in good agreement with EPA values. Unit conversions were reviewed and found to be correctly applied. Possible background errors in geometry were investigated and found to have an insignificant effect. (0 Probable failure to transfer all sample residue to the counting planchet Analysts are being tested using in-house and other EPA spikes. 93
US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER 90
. 60 u
D. 40 g r 20 0 t-----.~-.-~-----~.....----~-----.....-.....-~-----~.....----,~--~.----~------~----t 1981 1982 1983 1984 1985 a Tl +/-3 sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER ccont.l 80 60 u a. 40 I I 20 i I 0
' d 1 li f-~--~--~~..--~--~........~---..---~...-~--~---~~.--~--~.......~--~~
1985 1988 1987 1988 1989 1990 1991 1992 a Tl+/- 3S o EPA+/-3 S
US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER 60 40 j u Q. 20 0
.201981
..........-----------------------------------------------------------------------.....---t 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 a Tl +/-3 sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM TRITIUM IN WATER 5000------------------------------------, 4000
.* 3000 I =
u
- a. I 2000 1000 0 ""-----....-------__.;=---------~---.------.. . . ----.-------1 1981 1982 1983 1984 1985 a Tl+/-3slgma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM TRITIUM IN WATER (cont.) 14000
- 12000
.* 10000 * -u A.
8000
- I
- 6000.
~
*5
.~J *5.
., 11 4000 f~ j f tt t la .,
r 2000. 0 j i I I I r I la Ia 1985 1986 1987 1988 1989 1990 1991 1992 a Tl+/-3S o EPA+/-3S
US EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER 220...-------------------------,, 180 140 u A. 100 60
-20+----.....-----............------~,------.---....-------.-------T"-------,.-----.---.........--t 1981 I 1982. 1983 1984 a Tl+/- 3sigma o EPA+/- 3 sigma
US EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER 100 80 I u Q. 60 40 20 l hi~t HH, ; i5 Ii 0
-20+-~..-.----........---r~---r-~--.-~-,-~--~,-----,.......-----,.~---r-~--.-~-r-~-,--~-r-----t 1984 1985 1986 1987 1988 1989 1990 1 g91 1992 a Tl +/-3 Sigma o EPA+/- 3 Sigma
US EPA CROSS CHECK PROGRAM GROSS BETA IN WATER 220 200 180 160 140 --* 120 u Q. 100 80 60 20 0
-20+----.----------.~------.~----~..------~.....----.-~-------...----------.--------,
1981 1982 1983 1984 a Tl +/-3sigma o EPA+/- 3 sigma
US EPA CROSS CHECK PROGRAM GROSS BETA IN WATER 180 160 140 120
- 100
()
- a. 80 I
eo I
,4()
20
~
; ; ~ r; I f rr t
~ ~
-20 0
1984
' 1985 1986 1987 a Tl +/-3sigma o EPA+/- 3 sigma
US EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (Cont.) 120 a 100
- 90 u
D. 60 40 20 a a a a a a a 0 a
-20""--------~~-------........------------------------------------------------.......
1987 1988 1989 1990 1991
------t 1992 a Tl +/-3 sigma o EPA+/- 3 sigma
- US EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 120 100 a
-- 80 I u 60 11:1. 20 it ,; 0
~ Ii di i I t-_.-..,.,- - - - . . - - - - - . . - - - - . - - - . - - - - - - - - - - - - . - - - -.......
1981 1982 1983 1984 1985 1988 1987 1988 1989 1080
-----.-----1 1991 1992 a Tl +/-3sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM IODINE-131 IN MILK 120 100 -.-u.... 80 A. 60 20 I J 0 D C I
'i aa
+-~------------.-------..----.-----------------.---.---------.----------~----,----r---.---t 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 D. Tl+/-3sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM STRONTWM-90 IN MILK 80 I 60
*E UI cw,
-H 40 a iH i IH I I 20 i a 0 i I .
-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 a Tl +/-3slgma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM STRONTWM-89 IN MILK 80
*E at 60 l
-H s: ~ a 1 I a
~
20 1l i l 0 0 0
-20+--...------.-----"""'T"""-....------------r----...----,,-----.---r---.r-----w-----t 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990
- 1991 1992 a Tl +/-3slgma o
- EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK 26()()-,.-------------------------------------. 2200
- 1800 u
a. 1400 1000 eoo-----------------------------------------.----.....--....--1 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 a Tl+/- 3sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK 90 u D. 60 l 40 20 o-1--------------------------...---.-....----,...---.---r-~--1 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 a Tl +/-3 sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICUIATES eo---------------------------. 70 - 60-50 - ua. .. ii "1* . 0 40 - 30- 1, I 20 - I
}j I 1 \ \ ii f I ~l 10
- 0 I
l . . I I . I . I I I i I I I 1992 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 o Tl +/-3slgma o EPA i 3 sigma
US EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES 80"T-------------------------------------, 60 40 uQ. ii {! 20 0
+--........
1981
-----------------------------------------r--t 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 a Tl +/-3 sigma o EPA+/- 3 sigma
US EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICUIATES 80"T"---------------------------------- 60 uQ. 40 0 20 0
+-----------....-------------"T"-------....-----------""T""------1 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 a Tl +/- 3 Sigma o EPA+/- 3 Sigma
US EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICUI.ATES 140 120 100 D uQ. 0 60 40 a 20
-+---.----.---------------------------------T----r---,.---1 019811 1982 1983 1984 1985 1986 1987 1988 1989 1 D90 1991 1 992 o Tl +/-3 Sigma
- 08/25/89 EPA test lnvalJd. o EPA+/- 3 Sigma
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